ML042050505

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Section 5, 6 and Appendices
ML042050505
Person / Time
Site: Dresden, Quad Cities  Constellation icon.png
Issue date: 07/01/2004
From: Kuo P
Division of Regulatory Improvement Programs
To: Skolds J
Exelon Generation Co
Burton W, NRR/DRIP/RLEP, 415-2853
Shared Package
ML042050507 List:
References
Download: ML042050505 (34)
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Text

5. REVIEW BY THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS In accordance with Title 10, Part 54, of the Code of Federal Regulations (10 CFR Part54), the Advisory Committee on Reactor Safeguards (ACRS) will review the license renewal application (LRA) for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2. The ACRS Subcommittee on Plant License Renewal will continue its detailed review of the LRA after this report is issued. The applicant and the staff will meet with the full committee to discuss issues associated with the review of the LRA. After the ACRS completes its review of the LRA and the safety evaluation report (SER), the full committee will issue a report discussing the results of its review. This report will be included in an update to this SER. The staff will address any issues and concerns identified in that report.

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6. CONCLUSIONS The staff reviewed the license renewal application for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2, in accordance with Commission regulations and the NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants, dated July 2001. The standards for issuance of renewed license are provided in Title 10, Section 54.29, of the Code of Federal Regulations (10 CFR 54.29).

On the basis of its evaluation of the application, as discussed above, the staff concludes that the requirements of 10 CFR 54.29(a) have been met, and all open items and confirmatory items of this safety evaluation report have been resolved.

The staff notes that any requirements of Subpart A of 10 CFR Part 51 are documented in the final plant-specific supplement to the Generic Environmental Impact Statements issued on June 29, 2004 for Dresden, and June 30, 2004, for Quad Cities.

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APPENDIX A COMMITMENTS FOR LICENSE RENEWAL During the review of the Dresden/Quad Cities Nuclear Power Station (D/QCNPS) license renewal application (LRA) by the U.S. Nuclear Regulatory Commission (NRC) staff, the applicant made commitments related to aging management programs (AMPs) to manage aging effects of structures, systems, and components (SSCs) before the period of extended operation. The following table lists these commitments, along with the implementation schedule and the source of the commitment.

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Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

1) ASME Code, Existing program is credited. Both Dresden and Quad Cities will be A.1.1 Prior to the period of LRA Section B.1.1; Response to Section XI Inservice implementing RI-ISI and its alternative inspections for Class 1 and extended operation RAI 3.1-25 and RAI B.1.1, letter Inspection, Subsections 2 piping within the scope of license renewal. The requirements of IWB, IWC, and IWD ASME Code,Section XI will be implemented in accordance with 10 RS-03-181, dated October 3, CFR 50.55(a). 2003
2) Water Chemistry Existing program is credited. The program will be A.1.2 Prior to the LRA Section B.1.2 enhanced to provide increased sampling to verify period of corrective actions are taken to address abnormal extended chemistry conditions. The Quad Cities procedure for operation turbine building sample panel collection will be revised to assure maintenance of the integrity of chemistry samples.
3) Reactor Head Existing program is credited. A.1.3 Ongoing LRA Section B.1.3 Closure Studs
4) BWR Vessel ID Existing program is credited A.1.4 Ongoing LRA Section B.1.4 Attachment Welds
5) BWR Feedwater Existing program is credited. The program will be A.1.5 Prior to the LRA Section B.1.5; Response to Nozzle enhanced to implement the recommendations of period of Supplemental RAI B.1.5, letter Revision 1, Version A of report GE-NE-523-A71-0594- extended RS-03-223, dated November A, Revision 1, which was approved by the NRC staff. operation 21, 2003
6) BWR Control Existing Program is Credited A.1.6 Ongoing LRA Section B.1.6 Rod Drive Return Line Nozzle A-3

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

7) BWR Stress Existing program is credited. The program will be A.1.7 End of 2018 (plus LRA Section B.1.7; Response to Corrosion Cracking enhanced to include an additional ultrasonic or minus 2 years) Supplemental RAI 3.1-1, letter examination of the Quad Cities Unit 2 reactor vessel RS-03-235, dated December head crack (detected in 1990) to verify that the relevant 17, 2003 indication has remained essentially unchanged. The examination will be completed by the end of 2018 (plus or minus 2 years).
8) BWR Existing program is credited. A.1.8 Ongoing LRA Section B.1.8 Penetrations A-4

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

9) BWR Vessel Existing program is credited. The program will be A.1.9 As approved by the LRA Section B.1.9; Response to RAIs Internals enhanced as follows: NRC 4.2-BWRVIPs and B.1.9, letter RS 181, dated October 3, 2003; responses (1) Additional inspections will be performed when new to Supplemental RAIs 4.2-BWRVIP inspection techniques and tooling are developed, and B.1.9(d), letter RS-03-223, dated incorporated into applicable BWRVIP document(s), and November 21, 2003; RS-04-080, dated approved by the NRC. May 27, 2004 (2) Dresden and Quad Cities agree to perform inspections of the top guide similar to inspections of the control rod drive housing guide tube. However, Exelon reserves the right to modify the above agreed upon inspection program should the BWRVIP-26 be revised in the future.

(3) Exelon has made commitments to ensure that the Dresden and Quad Cities steam dryers will maintain their structural integrity at EPU power levels for long-term operation and will not generate loose parts. These commitments have been submitted to the NRC for acceptance in a letter dated May 12, 2004. Should Exelons plans not be successful, Exelon will include the steam dryers in the scope of license renewal under 10 CFR 54.4(a)(2) and will provide the appropriate aging management in accordance with 10 CFR 54.37(b).

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Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

10) Thermal Aging and An aging management program will be implemented for thermal A.1.10 Prior to the period of LRA Section B.1.10 Neutron Irradiation aging and neutron irradiation embrittlement of CASS reactor extended operation Embrittlement of Cast internal components within the scope of license renewal. A Austenitic Stainless component specific evaluation for the loss of fracture toughness will Steel (CASS) be included. For those components where the loss of fracture toughness may affect the function of the component, an inspection will be performed as part of the ISI program.
11) Flow-Accelerated Existing program is credited. The program will be enhanced to A.1.11 Prior to the period of LRA Section B.1.11, response to RAI Corrosion include portions of the main steam and the reactor vessel head extended operation 3.1-18, letter RS-03-181, dated vent systems that are within the scope of license renewal. October 3, 2003
12) Bolting Integrity Existing program is credited. The program will be enhanced to do A.1.12 Prior to the period of LRA Section B.1.12; response to the following: extended operation Supplemental RAI 3.5-13, letter RS (1) Credit periodic in-service Inspection piping and component 227, dated December 5, 2003; preventive maintenance inspections, system engineering response to RAI 3.1-13, letter RS walkdowns, and routine walkdowns to inspect for leakage and 181, dated October 3, 2003; response visual indications of loose bolts; trend walkdown results to Supplemental RAI 3.1-13, letter RS-(2) Manage the loss of preload for closure bolting in the reactor 03-223, dated November 21, 2003; vessel system, recirculation pumps, reactor recirculation valves, response to RAI B.1.12(d), letter RS-reactor vessel head vent valves, and the reactor pressure boundary 03-181, dated October 3, 2003 portion of all other systems.

(3) Credit periodic inspections of the closure bolting in accordance with the ASME Code Section XI requirements.

(4) Inspect bolted joints of diesel generator system components, component bolted joint inspections in high-humidity/moisture areas (pump vaults), and reactor vessel-to-ring girder bolting.

(5) Enhance implementing procedure to reference NUREG-1339.

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Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

13) Open-Cycle Cooling Existing program is credited. The program will be enhanced to A.1.13 Prior to the period of LRA Section B.1.13; response to Water Program include periodic inspections of cooling water pump internal linings, extended operation Supplemental RAI B.1.13(a), letter RS-additional heat exchangers and sub-components, external surfaces03-235, dated December 17, 2003 of various submerged pumps, components in the high humidity/moisture environments of the pump vaults, and piping. At Dresden only, periodic visual inspections will be performed of strainer internals in the CCSW supply line to the main control room HVAC.
14) Closed-Cycle Existing program is credited. The program will be enhanced to A.1.14 Prior to the period of LRA Section B.1.14 Cooling Water Program provide monitoring of specific parameters in accordance with EPRI extended operation TR-107396 guidance. This will include provisions for monitoring parameters such as pH, specific gravity, freeze point, reserve alkalinity, percent glycol and suspended solids in glycol based systems as appropriate. At Dresden, the program will include monitoring of pH and ammonia in the diesel generator jacket water.
15) Inspection of Existing program is credited. The program will be enhanced to A.1.15 Prior to the period of LRA Section B.1.15 Overhead Heavy Load include specific inspections for rail wear and proper crane travel on extended operation and Light Load (Related the rails, and for corrosion of crane structural components.

to Refueling) Handling Systems

16) Compressed Air Existing program is credited. The program will be enhanced to A.1.16 Prior to the period of LRA Section B.1.16; response to Monitoring include periodic inspections on those portions of the instrument air extended operation Supplemental RAI B.1.16-01, letter RS-distribution piping in the scope of license renewal. The program will 04-073, dated May 18, 2004 also include additional air sample points representative of the in-scope piping. Additionally, at Dresden only, periodic blowdowns will be provided of the instrument air receiver tanks.
17) BWR Reactor Water Existing program is credited. A.1.17 Ongoing LRA Section B.1.17 Cleanup System A-7

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

18) Fire Protection Existing program is credited. The program will be enhanced as A.1.18 Prior to the period of LRA Section B.1.18; response to follows: extended operation Supplemental RAI B.1.18-01, letter RS-(1) Specific guidance will be provided to check fire doors for 03-222, dated November 20, 2003; wear and holes in skin. At Quad Cities only, the program will be NRC Aging Management Program revised to include the requirement to check fire door clearances. Audit Report, dated April 23, 2004 (2) Periodic inspections will be performed for corrosion on the external surfaces of piping and components for the carbon dioxide systems; and for the external surfaces of the Dresden halon system.

(3) Specific guidance will be provided for examining the fire pumps and the Dresden isolation condenser makeup pump diesel fuel supply systems for leaks during pump tests.

(4) Periodic capacity tests will be performed on the Dresden isolation condenser diesel-driven makeup pumps.

(5) At Dresden, frequency of inspections will be provided for fire doors and spill barriers.

(6) The program will be revised to perform a visual inspection (VT-1 or equivalent) on a 10% sample population of each type of fire seal on a refueling outage frequency. Additionally, the program will be revised to expand the sample population by 10% if any of the inspected seals are found to have abnormal degradation that could prevent the seal from performing its intended function.

19) Fire Water System Existing program is credited. The program will be enhanced as A.1.19 Prior to the period of LRA Section B.1.19 follows: extended operation (1) Periodic non-intrusive wall thickness measurements will be provided of selected portions of the fire water system.

(2) Periodic inspections will be performed on the external surfaces of submerged fire pumps, outdoor fire hydrants, and outdoor transformer deluge system components.

(3) Sampling of sprinklers will be performed in accordance with NFPA 25, "Inspection, Testing, and Maintenance of Water-Based Fire Protection Systems."

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Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

20) Above-ground Existing program is credited. The program will be enhanced as A.1.20 Prior to the period of LRA Section B.1.20; responses to Carbon Steel Tanks follows: extended operation Supplemental RAIs B.1.2 and B.1.20, (1) Periodic system engineer walkdowns will be performed on letter RS-03-222, dated November 20, the nitrogen storage tanks utilizing stand-alone procedures. 2003; NRC Aging Management (2) At Quad Cities, a one-time UT thickness inspection will be Program Inspection Report performed of the aluminum condensate storage tank or 05000237/2003010(DRS);

demineralized water storage tank. 05000249/2003010(DRS);

(3) At Dresden, periodic internal/external inspections of the 05000254/2003014(DRS);

aluminum storage tanks will be performed, and periodic UT 05000265/2003014(DRS), dated thickness inspections will be performed of the bottoms will be December 5, 2003 performed

21) Fuel Oil Chemistry Existing program is credited. The program will be enhanced to A.1.21 Prior to the period of LRA Section B.1.21; response to RAI include inspection of the fuel oil storage tank interiors for corrosion extended operation B.1.21, letter RS-03-180, dated during regularly scheduled tank cleanings. October 3, 2003
22) Reactor Vessel Existing program is credited. The program will be enhanced as A.1.22 Prior to the period of LRA Section 3.1.1.1.4, LRA Section Surveillance follows: extended operation B.1.22, response to RAI B.1.22, letter (1) The Integrated Surveillance Program (ISP) for the license RS-03-181, dated October 3, 2003; renewal period (in accordance with proposed BWRVIP-116) will be response to Supplemental RAI B.1.22, implemented when approved by the NRC. letter RS-03-223, dated November 21, (2) If BWRVIP-116 is not approved, a plant-specific surveillance 2003 plan will be provided for the license renewal period in accordance with Appendices G and H to 10 CFR Part 50 A-9

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

23) One-Time One-time inspection sampling will be performed on the following: A.1.23 Prior to the period of LRA Sections 3.2.1.1.3, 3.2.1.1.5, Inspection (1) at Dresden, spent fuel pool cooling and demineralizer system extended operation 3.5.1.1.6, and B.1.23; response to components for corrosion in stagnant locations Supplemental RAI B.1.23-2.1, letter (2) condensate and torus water components for corrosion in RS-04-014 dated January 26, 2004; stagnant locations response to RAIs 3.5-7 and 3.1-9, (3) compressed gas system piping components for corrosion letter RS-03-201 dated October 3, (4) compressed gas system flexible hoses for age related 2003; response to Supplemental RAI degradation 3.1-21(b), letter RS-03-223, dated (5) lower sections of carbon steel fuel oil and lubricating oil tanks November 21, 2003; response to for reduced thickness Supplemental RAIs B.1.2, B.1.2-1, and (6) fuel oil and lubricating oil piping and components for 3.1-21(a), letter RS-03-238, dated corrosion December 22, 2003; responses to (7) control room ventilation, EDG ventilation, SBO building Supplemental RAIs 3.5-15 and 3.5-17, ventilation, reactor building ventilation, and standby gas treatment letter RS-03-227, dated December 5, system components for loss of material 2003; letter RS-04-046, dated (8) HPCI lubrication oil hoses for age related degradation December 25, 2004 (9) non-safety-related vent and drain components for age related degradation (10) 10 CFR 54.4(a)(2) components for corrosion (11) piping exposed to containment atmosphere for loss of material (12) torus saddle supports to confirm condition of drywell radial beam lubrite baseplates (13) 10% of high and medium risk butt welds in ASME Code, Class 1, NPS < 4 in. piping (14) stainless steel components in CRD hydraulic system and stainless steel clevis pins in torus water environment for stress corrosion cracking; clevis pin interface with uncoated carbon steel in torus water environment for galvanic corrosion (15) sample of stainless steel standby liquid control system components not in reactor coolant pressure boundary section of SBLC system for cracking A-10

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

24) Selective Leaching A sample of components that are made of susceptible materials will A.1.24 Prior to the period of LRA Section B.1.24 of Materials be visually inspected for evidence of selective leaching. The extended operation sample will be expanded if failed conditions are identified.
25) Buried Piping and Existing program is credited. The program will be enhanced as A.1.25 Prior to the period of LRA Section B.1.25; response to RAI Tanks Inspection follows: extended operation B.1.25, letter RS-03-181, dated (1) A one-time visual inspection will be performed on the external October 3, 2003; response to surface of a section of buried ductile iron fire main piping (including Supplemental RAI B.1.25-1, letter RS-a mechanical joint).04-046, dated March 25, 2004 (2) A one-time internal UT of one buried steel tank per site will be performed.

(3) At Quad Cities, periodic leakage checks will be performed on buried carbon steel fuel oil storage tanks.

26) ASME Code, Existing program is credited. The program will be enhanced as A.1.26 Prior to the period of Response to RAI B.1.26, letter RS Section XI, Subsection follows: extended operation 180, dated October 3, 2003; responses IWE (1) The program will be based on the latest edition and addenda, to Supplemental RAIs 2.4-3, 3.5-5, which is approved by the NRC 12 months prior to the end of the 4.7.2.2-1, and 4.7.2.2-02, letter RS current 120-month inspection interval. 227, dated December 5, 2003; (2) The program will be updated in accordance with 10 CFR response to Supplemental RAI B.1.27, 50.55(a). letter RS-04-046, dated March 25, (3) Additional inspections of the Dresden Unit containment shell 2004; LRA Section B.1.26, response to for corrosion will be provided. RAI 3.5-6, letter RS-03-227, dated (4) Requirements will be provided in Quad Cities procedures to December 5, 2003 ensure that sand pocket drains are clear.

(5) The pressurized testing methodology will be credited for managing the aging of bellows.

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Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

27) ASME Code, Existing program is credited. The program will be enhanced to A.1.27 Prior to the period of LRA Section B.1.27; Open Item Section XI, Subsection include inspection of Class MC component supports consistent with extended operation 3.5.2.3.2.2-1; response to RAI 3.5-7, IWF NUREG-1801, Chapter III, Section B1.3. The ASME Code, Section letter RS-03-180, dated October 3, XI, Subsection IWF program will manage the aging of the following 2003; response to Supplemental RAI Class MC supports: 2.4-2, letter RS-03-0227, dated (1) Biological Shield to Containment Stabilizer December 5, 2003; response to (2) RPV Male Stabilizer Attached to Outside of Drywell Shell Supplemental RAI B.1.27, letter RS (3) RPV Female Stabilizer and Anchor Rods 046, dated March 25, 2004 (4) Suppression Chamber Ring Girder Vertical Supports and Base Plates (5) Suppression Chamber Saddle Supports and Base Plates (6) Suppression Chamber Seismic Restraints and Base Plates (7) Vent Header Vertical Column Supports
28) Appendix J of 10 Existing program is credited. A.1.28 Ongoing LRA Section B.1.28 CFR Part 50,
29) Masonry Wall Existing program is credited. A.1.29 Ongoing LRA Section B.1.29 Program A-12

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

30) Structures Existing program is credited. The program will be enhanced to add A.1.30 Prior to the period of LRA Sections B.1.30, 3.3.1.2.1, Monitoring Program the following which will be implemented prior to the period of extended operation 3.5.1.1.7, 3.5.1.2.6, and 3.5.1.2.7; extended operation: response to Supplemental RAI B.1.30, (1) inspections of structural steel components in secondary letter RS-03-227, dated December 5, containment, flood barriers, electrical panels and racks, junction 2003; response to Supplemental RAI boxes, instrument panels and racks, and offsite power structural B.1.27, letter RS-04-046, dated March components and their foundations, and the Quad Cities discharge 25, 2004; response to Open Item canal weir as part of the ultimate heat sink 3.5.2.3.2-1, letter RS-04-057, dated (2) periodic reviews of chemistry data on below-grade water to April 9, 2004 and letter RS-04-088 confirm that the environment remains non-aggressive for dated June 22, 2004, teleconference aggressive chemical attack of concrete or corrosion of embedded summary dated July 13, 2004.

steel (3) inspection of a sample of non-insulated indoor piping external surfaces at locations immediately adjacent to periodically inspected piping supports and inspection of standard components such as snubbers, struts, and spring cans.

(4) program reference to specific insulation inspection criteria for existing cold weather preparation and inspection procedures for outdoor insulation, and the establishment of new inspections for various indoor area piping and equipment insulation (5) inspection parameters for non-structural joints, roofing, grout pads and isolation gaps (6) Extension of inspection criteria to the structural steel, concrete, masonry walls, equipment foundations, and component support sections of the program (7) VT-3 visual inspections of 15% of the non-exempt Class MC pipe supports once every 10 years A-13

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

31) RG 1.127, Existing program is credited. The program will be enhanced to add A.1.31 Prior to the period of LRA Section B.1.31; response to Inspection of Water- the following: extended operation Supplemental RAIs 3.5-12 and B.1.31, Control Structures (1) monitoring of crib house concrete walls and slabs with an letter RS-03-227, dated December 5, Associated with Nuclear opposing side in contact with river water 2003 Power Plants (2) inspection for structural integrity of concrete and steel components and identification of specific types of components to be inspected (3) periodic monitoring of the Dresden discharge outfall concrete structure (4) at Quad Cities, periodic inspections of the concrete of the discharge flume/canal and the weir gate in the discharge canal
32) Protective Coating Existing program is credited. The program will be enhanced as A.1.32 Prior to the period of LRA Section B.1.32 Monitoring and follows: extended operation Maintenance Program (1) visual inspection of Service Level I coatings near sumps or screens associated with the emergency core cooling system (2) pre-inspection review of previous reports so that trends can be identified for the program (3) analysis of coating failures to determine reasons for failures
33) Electrical Cables A program will be developed that is consistent with NUREG-1801 A.1.33 Prior to the period of LRA Section B.1.33; response to RAI and Connections Not AMP XI.E1 for electrical cables and connections installed in extended operation B.1.33-3, letter RS-03-177, dated Subject to 10 CFR 50.49 adverse localized environments not subject to 10 CFR 50.49 October 3, 2003 Environmental environmental qualification requirements.

Qualification Requirements

34) Metal Fatigue of Existing program is credited. The program will be enhanced to A.1.34, A.3.4 Prior to the period of LRA Sections 4.3.1, 4.3.2, 4.3.3.1, Reactor Coolant utilize the EPRI-licensed FatiguePro computer program for extended operation. 4.6.1, 4.6.2 and B.1.34; response to Pressure Boundary monitoring fatigue at bounding locations for reactor pressure RAI B.1.34, letter RS-03-180, dated vessel, Class I piping, torus, torus vents, and torus attached piping October 3, 2003 and penetrations, SRV discharge lines, and the Dresden isolation condenser.

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Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

35) Environmental Existing program is credited. A.1.35 Ongoing LRA Section B.1.35 Qualification (EQ) of Electrical Components
36) Boraflex Monitoring Existing program is credited. A.1.36 Ongoing LRA Section B.1.36
37) Electrical Cables A program will be developed to manage aging of cables in sensitive A.1.37 Prior to the period of LRA Section B.1.37; Responses to Not Subject to 10 CFR instrumentation circuits with low-level signals in the Nuclear extended operation RAIs 3.6-9 and B.1.33-1, letter RS 50.49 Environmental Instrumentation Systems and Radiation Monitoring Systems. The 177, dated October 3, 2003; response Requirements Used in program will include a review of calibration and surveillance results, to Supplemental RAI 3.6-09, letter RS-Instrument Circuits and cable testing every 24 months (SRM, IRM circuits) for cable 03-238, dated December 22, 2003 aging degradation before the period of extended operation and every 10 years thereafter. This program applies to the cables of the Nuclear Instrumentation Systems which includes source range monitors, intermediate range monitors, local power range monitors, and Radiation Monitoring Systems which includes drywell high range radiation monitors, main steam line radiation monitors, and the steam jet air ejector radiation monitors.
38) Inaccessible At Dresden, a new condition monitoring program will be provided in A.1.38 Prior to the period of LRA Section B.1.38; Response to Medium-Voltage Cables accordance with NUREG-1801, AMP XI.E3 to manage aging of five extended operation Supplemental RAI 3.6-3, letter RS Not Subject to 10 CFR inaccessible medium-voltage cables feeding the service water 222, dated November 20, 2003 50.49 Environmental pumps. The cables will be tested at least once every ten years.

Requirements The end of the cribhouse duct bank will be inspected annually to verify that the duct run is not plugged with debris.

39) Corrective Action Existing program is credited. A.2.1 Ongoing LRA Section B.2.1 Program A-15

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

40) Periodic Inspection A program will be developed and implemented to periodically A.2.2 Prior to the period of LRA Section B.2.2; response to RAI of Non-EQ, Non- inspect non-segregated bus ducts that connect the reserve extended operation 3.6-4, letter RS-03-177, dated October Segregated Electrical auxiliary transformers (RATs) to 4160V ESS buses, the non- 3, 2003; responses to Supplemental Bus Ducts segregated bus ducts that connect the EDG to the ESS buses, and, RAIs 3.6-4, 3.6-7, and B.2.2-01, letter for Dresden only, the non-segregated bus ducts that connect ESS RS-03-227, dated December 5, 2003; buses. The bus duct internal components and materials will be response to Supplemental RAI B.2.2-1, visually inspected for signs of aging degradation. The program will letter RS-03-238, dated December 22, include the following: 2003.

(1) inspection of accessible normally energized non-segregated bus duct internal components such as insulation materials, bus duct support pieces, gaskets, insulating boots, taped connections, and bus bar sleeves for material surface anomalies for non-segregated bus duct that connects the RATs to the 4160V ESS buses (2) inspection of bus bar insulation material at the accessible bolted connections of the non-segregated bus duct that connects the RATs to the 4160V ESS buses (3) inspection of 10% of the splice insulation material at the bolted connections (including all visible insulation in both directions beyond the location of the bolted connection splice insulation inspected) for the non-segregated bus duct that connects the EDG to the ESS buses and, for Dresden only, the non-segregated bus duct that connects the ESS buses for signs of aging degradation that indicate possible loose connections (4) inspections for the presence of dirt or moisture in the bus duct A-16

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

41) Periodic Inspection Existing program is credited. The program will be enhanced to A.2.3 Prior to the period of LRA Section B.2.3; letter RS-03-235, of Ventilation System include inspection of aging of all elastomers, flexible boots, access extended operation dated December 17, 2003 Elastomers door seals and gaskets, filter seals and gaskets, and RTV silicone used as a duct sealant, in the components of the SBO ventilation and Reactor Building ventilation systems for Dresden, and the SBO ventilation and EDG Room ventilation systems for Quad Cities.

The inspections will be performed to detect cracking, loss of material, and other evidence of aging. Tests of seals for hardening will be included if evidence of aging is found.

42) Periodic Testing of Existing program is credited. A.2.4 Ongoing LRA Section B.2.4 Drywell and Torus Spray Nozzles
43) Lubricating Oil Existing program is credited. The program will be enhanced to A.2.5 Prior to the period of LRA Section B.2.5; Response to RAI Monitoring Activities include those components exposed to an environment of lubricating extended operation B.1.23-2, letter RS-03-180, dated oil in the following systems: October 3, 2003; Supplemental RAIs (1) the reactor core isolation cooling system (Quad Cities only) B.1.23-02.3 and B.1.23-02.4, letter RS-(2) the main generator hydrogen seal oil system (Quad Cities04-014, dated January 26, 2004 only)

(3) the high pressure coolant injection system (4) the emergency diesel generator and auxiliaries system (5) the station blackout diesel system (6) the electro-hydraulic control system A-17

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

44) Heat Exchanger An aging management program will be developed and implemented A.2.6 Prior to the period of LRA Section B.2.6; response to Test and Inspection for heat exchangers in the scope of license renewal that are not extended operation Supplemental RAI 3.1-11, letter RS Activities tested and inspected by the Open-Cycle Cooling Water System and 223, dated November 21, 2003; Closed-Cycle Cooling Water System aging management programs. response to Supplemental RAI 3.1-11, Specifically, for the Dresden isolation condensers, the letter RS-03-238, dated December 22, augmentation activities identified in NUREG-1801, lines IV.C1.4-a 2003 and IV.C1.4-b to manage loss of material and cracking will also be included in this aging management program, and will provide the following:

(1) temperature and radioactivity monitoring of the shell-side (cooling) water (2) eddy current testing of the tubes (3) visual inspections of the channel head, tube sheets, and internal surfaces of the shell

45) Generator Stator Existing program is credited. A.2.7 Ongoing LRA Section B.2.7 Water Chemistry Activities
46) Periodic Inspection An aging management program will be developed and implemented A.2.8 Prior to the period of LRA Section B.2.8; Response to RAI of Plant Heating System to inspect components in the Plant Heating system once before the extended operation B.1.23, letter RS-04-046, dated March end of the current operating term and periodically at intervals not to 25, 2004 exceed once every 5 years during the period of extended operation.
47) Time-Limited Aging Revised P-T limits will be prepared and submitted to the NRC for A.3.1.5 Prior to the period of LRA Section 4.2.5; response to RAI Analysis (TLAA) - approval prior to the start of the extended period of operation using extended operation 4.3.0, letter RS-03-180, dated October Neutron Embrittlement of an approved fluence methodology for Dresden and Quad Cities. 3, 2003 the Reactor Vessel and Internals A-18

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

48) TLAA - Metal The Dresden Unit 2 jet pump riser braces will be repaired or A.3.2.2.1 Prior to the period of LRA Section 4.3.2.2; response to RAI Fatigue replaced prior to the period of extended operation. extended operation 4.3.0, letter RS-03-180, dated October 3, 2003; response to RAI 4.3.2.2, letter RS-03-180, dated October 3, 2003 Plant-specific calculations will be performed for applicable locations A.3.2.4 Prior to the period of LRA Section 4.3.4; response to identified in NUREG/CR 6260, "Application of NUREG/CR-5999 extended operation Supplemental RAI 4.3.4, letter RS Interim Fatigue Curves to Selected Nuclear Power Plant 235, dated December 17, 2003 Components," for older-vintage BWR plants, to assess potential effects of reactor coolant on component fatigue life in accordance with 10 CFR 54.21(c)(1)(ii). Exelon reserves the right to modify this position in the future based on the results of industry activities currently underway, or based on other results of improvements in methodology, subject to NRC approval prior to changes in this position.
49) TLAA - A reanalysis will be applied to EQ components now qualified for the A.3.3 Prior to the period of LRA Section 4.4; response to RAI Environmental current operating term of 40 years. The EQ Binders for components extended operation 4.3.0, letter RS-03-180, dated October Qualification of Electrical within the scope of 10 CFR 50.49 will be updated to include 3, 2003 Equipment environmental conditions associated with EPU implementation together with an extended operating period of 60 years.

A-19

Appendix A - D/QCNPS Commitment List Associated with Renewal of the Operating Licenses Item Number Commitment UFSAR Implementation Source Supplement Schedule Location (LRA App. A)

50) TLAA - Other Plant- The corrosion rate assumptions used in the calculation of the A.3.5.2.1 Prior to the period of LRA Section 4.7.2.2 Specific TLAAs drywell steel plate remaining thickness at the sand pocket level will extended operation be confirmed by a Dresden Unit 3 UT inspection prior to the period of extended operation. The results will be used to revise the associated corrosion calculation and validate that an acceptable wall thickness will remain to the end of the 60-year licensed operating period.

The corrosion rate assumptions used in the calculation of the A.3.5.2.2 Prior to the period of LRA Section 4.7.2.3 ECCS Suction strainer flange remaining thickness will be confirmed extended operation by an ultrasonic inspection. One bounding inspection will be performed and results will be used to validate the corrosion rate for both sites. Based upon the results of the inspection, a revised galvanic corrosion calculation will be performed to ensure acceptable wall thickness to the end of the 60-year licensed operating period.

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APPENDIX B CHRONOLOGY This appendix contains a chronological listing of correspondence between the U.S. Nuclear Regulatory Commission (NRC) staff and Exelon Generation Company, LLC (Exelon), related to the NRC staffs review, under Title 10, Part 54, of the Code of Federal Regulations (10 CFR Part 54), of Exelon's license renewal application (LRA) for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2. All documents, with the exception of those containing proprietary information, have been placed in the Commission's Public Document Room, at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, and are available electronically from the Public Electronic Reading Room found on the Internet at http://www.nrc.gov/reading-rm.html. From this site, the public can gain access to the NRC's Agencywide Documents Access and Management System (ADAMS), which provides text and image files of the NRC's public documents in the Publicly Available Records (PARS) component of ADAMS. The ADAMS accession numbers for each document are included below.

January 3, 2003 Letter from Mr. Jeffrey A. Benjamin, Exelon Generating Company, LLC (Exelon) to the NRC, submitting the application for the renewal of the operating licenses for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Accession No. ML030090203)

January 24, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding the Notice of Receipt and Availability of the application for the renewal of the operating licenses for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Accession No. ML030240603)

February 7, 2003 Letter from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the Aging Management Review Aid and revised table links between LRA Chapters 2 and 3 (Accession No. ML030500245)

February 26, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding the Notice of Acceptance for Docketing and Opportunity for Hearing associated with the application for the renewal of the operating licenses for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 (Accession No. ML030570654)

April 17,2003 Letter from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the Corrected Fluence Tables for Dresden Nuclear Power Station, Units 2 and 3, associated with LRA (Accession No. ML031190598)

May 5, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding revision to the NRCs review schedule (Accession No. ML031260004)

B-1

July 21, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding the first set of Request for Additional Information (RAIs) associated with the LRA (Accession No. ML032020080)

July 21, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding the second set of Request for Additional Information associated with the LRA (Accession No. ML032020170)

August 4, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding the third set of Request for Additional Information associated with the LRA (Accession No. ML032180267)

August 4, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding the fourth set of Request for Additional Information associated with the LRA (Accession No. ML032180382)

August 7, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding the fifth set of Request for Additional Information associated with the LRA (Accession No. ML032310093)

September 9, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding a Supplemental Request for Additional Information associated with the LRA (Accession No. ML032530371)

October 3, 2003 Letter (RS-03-177) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the requested additional information (Accession No. ML032810579)

October 3, 2003 Letter (RS-03-178) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the requested additional information (Accession No. ML032810563)

October 3, 2003 Letter (RS-03-179) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the requested additional information (Accession No. ML032810692)

October 3, 2003 Letter (RS-03-180) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the requested additional information (Accession No. ML032820273)

October 3, 2003 Letter (RS-03-181) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the requested additional information (Accession No. ML032810682)

October 15, 2003 Letter (RS-03-201) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the requested additional information (Accession No. ML033010396)

B-2

October 20, 2003 Letter from the NRC to Mr. John L. Skolds, Exelon, forwarding an Inspection-related Open Item associated with the LRA (Accession No. ML032940056)

November 14, 2003 E-mail from T. Kim to A. Fulvio November 20, 2003 Letter (RS-03-222) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting supplemental information (Accession No. ML033320342)

November 21, 2003 Letter (RS-03-223) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting supplemental information (Accession No. ML033360714)

December 5, 2003 Letter (RS-03-227) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting supplemental information (Accession No. ML033500404)

December 12, 2003 Letter (RS-03-232) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting supplemental information (Accession No. ML033580647)

December 17, 2003 Letter (RS-03-235) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting supplemental information (Accession No. ML033580635)

December 22, 2003 Letter (RS-03-238) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting supplemental information (Accession No. ML033640630)

January 26, 2004 Letter (RS-04-14) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting supplemental information (Accession No. ML040340487)

February 3, 2004 Letter (RS-04-020) from Mr. Patrick R. Simpson, Exelon, to the NRC, Consolidated List of Commitments for License Renewal (Accession No. ML040420164)

March 5, 2004 Letter (RS-04-039) from Mr. Patrick R. Simpson, Exelon, to the NRC, Amendment to the Application for Renewed Operating Licenses for Dresden and Quad Cities Nuclear Power Stations (Accession No. ML040711186)

March 25, 2004 Letter (RS-04-046) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting the requested supplemental information (Accession No. ML040900466)

April 9, 2004 Letter (RS-04-057) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting responses to the draft SER Open Items and Confirmatory Items (Accession No. ML041070456)

April 23, 2004 Audit Report Related to the License Renewal Application for Dresden Nuclear Power Station and Quad Cities Nuclear Power Station May 18, 2004 Letter (RS-04-073) from Mr. Patrick R. Simpson, Exelon, to the NRC, submitting supplemental information (Accession No. ML041480178)

B-3

May 27, 2004 Letter (RS-04-080) from Mr. Keith R. Jury, Exelon, to the NRC, License Renewal Commitment for Scoping of Steam Dryers and the Dresden and Quad Cities Nuclear Power Stations (Accession No. ML041550270)

June 22, 2004 Letter (RS-04-088) from Mr. Patrick R. Simpson, Exelon to the NRC, submitting supplemental information (Accession No. ML041820207)

June 29, 2004 Final Supplement 17 to the Generic Environmental Impact Statement Regarding License Renewal for Dresden Nuclear Power Station, Units 2 and 3 (Accession Number ML041830675)

June 30, 2004 Final Supplement 16 to the Generic Environmental Impact Statement Regarding License Renewal for Quad Cities Nuclear Power Station, Units 1 and 2 (Accession Number 041830462)

July 13, 2004 Summary of telephone conference held on July 13, 2004, between the U.S.

Nuclear Regulatory Commission and the Exelon Generation Company Regarding the Resolution of Open Item 3.5.2.3.2-1 and Confirmatory Item 3.0.3.14.2-1 B-4

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APPENDIX C PRINCIPAL CONTRIBUTORS NAME RESPONSIBILITY T. Kim Project Manager R. Auluck Project Manager W. Burton Project Manager B. Wong Project Manager H. Ashar Mechanical Engineering S. Bailey Mechanical Engineering T. Chan Management Supervision K. Chang Technical Support K. Corp Technical Support K. Coyne Quality Assurance P. Y. Chen Technical Support S. Coffin Management Supervision B. Elliot Materials Engineering J. Fair Mechanical Engineering T. Ford Reactor Systems G. Galletti Quality Assurance R. Goel Plant Systems M. Hartzman Civil Engineering G. Hatchett Plant Systems R. Hernandez-Figueroa Plant Systems J. Honcharik Materials Engineering N. Iqbal Plant Systems V. Klco Plant Systems T. Koshy Electrical Engineering P.T. Kuo Management Supervision A. Lee Mechanical Engineering S. Lee Management Supervision J. Lehning Plant Systems Y. Li Mechanical Engineering L. Lund Management Supervision J. Ma Mechanical Engineering K. Manoly Management Supervision R. McNally Mechanical Engineering C. Munson Civil Engineering M. Murphy Chemical Engineering Q. Nguyen Technical Support A. Pal Electrical Engineering P. Patnaik Materials Engineering P. Prescott Quality Assurance J. Rajan Civil Engineering M. Razzaque Reactor Systems D. Shum Plant Systems J. Strnisha Mechanical Engineering C-1

A. Stubbs Plant Systems D. Terao Management Supervision D. Thatcher Management Supervision H. Wagage Plant Systems H. Wang Technical Support S. Weerakkady Management Supervision L. Wheeler Environmental Project Manager B. Wong C. Wu Mechanical Engineering CONTRACTORS Contractor Technical Area Argonne National Laboratory Reactor Vessel, Internals, Reactor Coolant System, and Auxiliary Systems Brookhaven National Laboratory Containment, Structures, and Component Supports Information Systems Laboratories Fire Protection and Aging Management Programs Pacific Northwest National Laboratory Engineered Safety Features and Steam/Power Conversion Systems C-2

APPENDIX D REFERENCES This appendix lists the references used in preparing the safety evaluation report associated with the license renewal application for the Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2.

AMERICAN CONCRETE INSTITUTE (ACI)

ACI 301, Specifications for Structural Concrete for Buildings ACI 318-63, Building Code Requirements for Reinforced Concrete AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME)

ASME Boiler and Pressure Vessel Code, July 1989 ASME Boiler and Pressure Vessel Code,Section III, Rules for Construction of Nuclear Power Plant Components (through Summer 1979 addenda)

ASME Boiler and Pressure Vessel Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components ASME Boiler and Pressure Vessel Code,Section XI, Appendix G (1995 edition through 1996 addenda)

AMERICAN SOCIETY FOR TESTING AND MATERIALS (ASTM)

ASTM A307, Standard Specification for Carbon Steel Bolts and Steels, 60,000 psi Tensile Strength ASTM A325, Standard Specification for Structural Bolts, Steel, Heat-Treated, 120 ksi and 105 ksi Minimum Tensile Strength ASTM A490, Standard Specification for Heat-Treated Steel Structural Bolts, 150ksi Minimum Tensile Strength ASTM D975-1981, Standard Specification for Diesel Fuel Oils AMERICAN WATER WORKS ASSOCIATION (AWWA)

AWWA C203, AWWA Standard for Coal-Tar Protective Coatings and Linings for Steel Water Pipelines - Enamel and Tape - Hot Applied, 1966 BOILING WATER REACTOR VESSEL AND INTERNALS PROJECT (BWRVIP)

BWRVIP-05, BWR RPV Shell Weld Inspection Recommendations, September 1995 D-1

BWRVIP-18, Core Spray Internals Inspection and Flaw Evaluation Guidelines, July 1996 BWRVIP-25, BWR Core Plate Inspection and Flaw Evaluation Guidelines, October 1999 BWRVIP-26, Top Guide Inspection and Flaw Evaluation Guidelines, December 1996 BWRVIP-27, Standby Liquid Control System/Core Plate P Inspection and Flaw Evaluation Guidelines, April 1997 BWRVIP-38, Shroud Support Inspection and Flaw Evaluation Guidelines, September 1997 BWRVIP-41, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines, October 1997 BWRVIP-47, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines, December 1997 BWRVIP-48, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines, March 1998 BWRVIP-49, Instrument Penetration Inspection and Flaw Evaluation Guidelines, March 1998 BWRVIP-74, BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines, September 1999.

BWRVIP-75, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (NUREG-0313), October 1999 BWRVIP-76, BWR Core Shroud Inspection and Flaw Evaluation Guidelines, December 1999 BULLETINS (BL)

NRC BL-80-11, Masonry Wall Design, May 1980 CODE OF FEDERAL REGULATIONS 10 CFR 50.34, Contents of application; technical information, Section (a)(1) 10 CFR 50.48, Fire Protection 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants 10 CFR 50.55a, Codes and Standards 10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Light water Nuclear Power Reactors for Normal Operation 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events D-2

10 CFR 50.62, Requirements for Reduction of Risk from Anticipated Transients Without Scram (ATWS) Events for Light-Water-Cooled Nuclear Power Plants 10 CFR 50.63, Loss of All Alternating Current Power 10 CFR 50.65, Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants 10 CFR Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants 10 CFR Part 50, Appendix G, Fracture Toughness Requirements 10 CFR Part 50, Appendix H, Reactor Vessel Material Surveillance Program Requirements 10 CFR Part 51, Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions 10 CFR Part 54, Requirements for Renewal of Operating Licenses for Nuclear Power Plants 10 CFR Part 100, Reactor Site Criteria ELECTRIC POWER RESEARCH INSTITUTE (EPRI)

EPRI NP-5461, Component Life Estimation: LWR Structural Materials Degradation Mechanisms, September 1987 EPRI NP-5769, Degradation and Failure of Bolting in Nuclear Power Plants, Vols. 1 and 2, Project 2520-7, 1998 EPRI NSAC/202-L, Recommendations for an Effective Flow-Accelerated Corrosion Program EPRI TR-103515, BWR Water Chemistry Guidelines, BWRVIP-29 EPRI TR-103840 BWR Containment License Renewal Industry Report; Revision 1 July 1994 EPRI TR-103842, Class I Structures Industry Report EPRI TR-104873, Methodologies and Processes to Optimize Environmental Qualification Replacement Internals, February 1996 EPRI TR-105747, Guidelines for Reinspection of BWR Core Shrouds, BWRVIP-07, February 1996 EPRI TR-105759, An Environmental Factor Approach to Account for Reactor Water Effects in Light Water Reactor Pressure Vessel and Piping Evaluations D-3

EPRI TR-106092, Evaluation of Thermal Aging Embrittlement for Cast Austenitic Stainless Steel Components in LWR Coolant Systems, September 1997 EPRI TR-106740, BWR Core Spray Internals and Flaw Evaluation Guidelines, BWRIVP-18, July 1996 EPRI TR-107079, Revision 2, BWR Core Shroud Inspection and Flaw Evaluation Guidelines, BWRVIP-01, October 1996 EPRI TR-107285, BWR Top Guide Inspection and Flaw Evaluation Guidelines, BWRVIP-26, December 1996 EPRI TR-107286, BWR Standby Liquid Control System/Core Plate P Inspection and Flaw Evaluation Guidelines, BWRVIP-27, April 1997 EPRI TR- 107396, Closed Cooling Water Chemistry Guidelines, October 1997 EPRI TR-107515, Evaluation of Thermal Fatigue Effects on Systems Requiring Aging Management Review for License Renewal for the Calvert Cliffs Nuclear Power Plant EPRI TR-107521, Generic License Renewal Technical Issues Summary, April EPRI TR-107943, Environmental Fatigue Evaluations of Representative BWR Components EPRI TR-108705, BWR Vessel and Internals Project, Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection EPRI TR-108727, BWR Lower Plenum Inspection and Flaw Evaluation Guidelines, BWRVIP-47, December 1997 EPRI TR-108728, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines, BWRVIP-41, October 1997 EPRI TR-108823, BWR Shroud Support Inspection and Flaw Evaluation Guidelines, BWRVIP-38, September 1997 EPRI TR-108724, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines, BWRVIP-48, February 1998 EPRI TR-110356, Evaluation of Environmental Thermal Fatigue Effects on Selected Components in a Boiling Water Reactor Plant EPRI TR-112214, BWR Vessel and Internals Project, Proceedings: BWRVIP Symposium, November 12-13, 1998 EPRI TR-113596, BWR Vessel and Internals Project BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines D-4

EPRI TR-114232, BWR Core Shroud Inspection and Flaw Evaluation Guidelines, BWRVIP-76, November 1999 EPRI TR-113596, BWR Vessel and Internals Project BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines, BWRVIP-74, September 1999 EPRI TR-107396, Closed Cooling Water Chemistry Guidelines GENERIC LETTERS (GLs)

NRC GL 85-20, Resolution of Generic Issue 69: High Pressure Injection/Makeup Nozzle Cracking in Babcock and Wilcox Plants, November 11,1985 NRC GL 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, 1989 NRC GL 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations, July 12, 1988 NRC GL 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment, August 8, 1988 NRC GL 89-13, Service Water System Problems Affecting Safety-Related Equipment, July 18, 1989 NRC GL 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping, June 1990 NRC GL 91-17, Resolution of Generic Safety Issue 29: Bolting Degradation or Failure in Nuclear Power Plants, October 1991 NRC GL 92-01, Revision 1, Supplement 1, Reactor Vessel Structural Integrity, May 18, 1995 NRC GL 92-08, Thermo-Lag 330-1 Fire Barriers, December 1992 NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks, June 26, 1996 GENERIC SAFETY ISSUES (GSIs)

GSI-166, Adequacy of the Fatigue Life of Metal Components GSI-168, Environmental Qualification of Electrical Components GSI-190, Fatigue Evaluation of Metal Components for 60-Year Plant Life INFORMATION NOTICES (INs)

NRC IN 87-67, Lesson Learned from Regional Inspections of Licenses Actions in Response to IE Bulletin 80-11, December 31, 1987 D-5

NRC IN 91-46, Degradation of Emergency Diesel Generator Fuel Oil Deliver Systems, July 1991 NRC IN 92-20, Inadequate Local Leak Rate Testing, March 1992 INSPECTION AND AUDIT REPORTS NRC Inspection Report 50-237/03-04(DRS); 50-249/03-04(DRS); 50-254/03-04(DRS); 50-265/03-04(DRS), Dresden Nuclear Power Station, Quad Cities Nuclear Power Station, NRC License Renewal Scoping/Screening Inspection, September 15, 2003 NRC Inspection Report 50-237/03-10(DRS); 50-249/03-10(DRS); 50-254/03-14(DRS); 50-265/03-14(DRS), Dresden Nuclear Power Station, Quad Cities Nuclear Power Station, NRC License Renewal Aging Management Program Inspection, December 5, 2003 INSTITUTE OF ELECTRICAL AND ELECTRONICS ENGINEERS (IEEE)

ANS/IEEE Std. 450-1980, IEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Storage Batteries for Generating Stations and Substations IEEE Std. 323-1974, Qualifying Class 1E Equipment for Nuclear Power Generating Stations, 1974 IEEE 43-1974, Recommended Practice for Testing Insulation Resistance of Rotating Machinery IEEE 95-1977, Recommended Practice for Insulation Testing of Large AC Rotating Machinery with High Direct Voltage NATIONAL FIRE PROTECTION ASSOCIATION (NFPA)

NFPA-25, Standard for the Inspection, Testing, and Maintenance of Water-Based Fire Protection Systems NUCLEAR ENERGY INSTITUTE NEI 95-10, Revision 3, Industry Guideline for Implementing the Requirements of 10 CFR Part 54The License Renewal Rule, August 2001 NUREG REPORTS NUREG-0588, Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment, November 1979 NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, July 1980 NUREG-0619, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking, Resolution of Generic Technical Activity A 10, November 1980 NUREG-0737, Clarification of TMI Action Plan Requirements, November 1980 D-6

NUREG-1275, Volume 3, Operating Experience Feedback ReportService Water System Failure and Degradations, March 1993 NUREG-1339, Resolution of Generic Safety Issue 29: Bolting Degradation or Failure in Nuclear Power Plants, June 1990 NUREG-1526, Lessons Learned from Early Implementation of Maintenance Rule at Nine Nuclear Power Plants, June 1995 NUREG-1568, License Renewal Demonstration Program: NRC Observations and Lessons Learned, December 1996 NUREG-1800, "Standard Review Plan for the Review of License Renewal Applications for Nuclear Power Plants," April 2001 NUREG-1801, Generic Aging Lessons Learned Report, July 2001 NUREG/CR-5704, Effects of LWR Coolant Environment on Fatigue Design Curves of Austenitic Stainless Steels, April 1999 NUREG/CR-6260, Application of NUREG/CR-5999, Interim Fatigue Curves to Selected Nuclear Power Plant Components, March 1995 NUREG/CR-6335, Fatigue Strain-Life Behavior of Carbon and Low-Alloy Steels, Austenitic Stainless Steels, and Alloy 600 in LRA Environments, August 1995 NUREG/CR-6384, Literature Review of Environmental Qualification of Safety-Related Electric Cables, Vol. 1, Brookhaven National Laboratory, prepared for the NRC, April 1996 NUREG/CR-6583, Effects of LWR Coolant Environments in Fatigue Design Curves of Carbon and Low-Alloy Steels, March 1998 REGULATORY GUIDES (RGs)

NRC RG 1.46, Revision 0, Protection Against Pipe Whip Inside Containment, withdrawn August 11, 1985 NRC RG 1.89, Revision 1, Environmental Qualification of Certain Electrical Equipment Important to Safety for Nuclear Power Plants, June 1984 NRC RG1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988 NRC RG 1.154, Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors NRC RG DG 1.188, "Standard Format and Content for Applications to Renew Nuclear Power Plant Operating Licenses" D-7

U.S. DEPARTMENT OF ENERGY (DOE)

SAND 93-7070.UC-523, Aging Management Guideline for Commercial Nuclear Power Plants -

Heat Exchangers July 1984 SAND 96-0344, Aging Management Guideline for Commercial Nuclear Power Plants -

Electrical Cables and Terminations, United States Department of Energy USA STANDARDS INSTITUTE (USASI)

ANSI USAS B31.1.0, USA Standard Code for Pressure Piping, 1968 ANSI USAS B31.7, USA Standard Code for Pressure Piping, Nuclear Power Piping, 1968 USAS B31.7, Nuclear Power Piping Exelon Controlled Documents Desktop Guide, Revision 2, Scoping & Screening of Systems, Structures and Components GE-NE-LRTI-2000, Revision 6, Technical Instruction for Exelon Dresden/Quad Cities License Renewal Project - Scoping and Screening of Systems, Structures and Components for License Renewal LRTI-16, Revision 0, Identification of Non Safety Related Structures and Components Which Spatially or Structurally Interact With Safety Related Systems PP-DRE Revision 03 SBO, Systems and Structures Relied Upon to Demonstrate Compliance with 10 CFR 50.63 (Station Blackout) Dresden Station - Units 2 and 3 PP-DRE-QDC Revision 02 AP, Active/Passive Classification and Intended Function Determination of Structures and Components PP-DRE-QDC Revision 01 SPACES, Scoping and Screening Position Paper for Electrical Components based on Electrical Spaces Approach for Aging Management Review PP-QDC Rev.03 SBO, Systems and Structures Relied Upon to Demonstrate Compliance with 10CFR50.63 (Station Blackout) Quad Cities Station - Units 1 and 2" PP-QDC-DRE Rev 00 IN, Treatment of Pipe/Equipment Insulation During Scoping and Screening Systems for License Renewal D-8

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