RS-16-128, Second 10 CFR 54.21(b) Annual Amendment to the License Renewal Application
| ML16160A329 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/08/2016 |
| From: | Gallagher M Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-16-128, TAC MF5346, TAC MF5347 | |
| Download: ML16160A329 (6) | |
Text
Michael P. Gallagher Exelon Nuclear Exelon Generation Vice President License Renewal and Decommissioning 200 Exelon Way Kennett Square, PA 19348 610 765 5958 Office 610 765 5658 Fax www.exeloncorp.com m1chaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 RS-16-128 June 8, 2016 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374
Subject:
Second 10 CFR 54.21 (b) Annual Amendment to the LaSalle County Station, Units 1 and 2, License Renewal Application (TAC Nos. MF5347 and MF5346)
References:
- 1. Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon),
to NRC Document Control Desk, dated December 9, 2014, "Application for Renewed Operating Licenses"
- 2. Letter from Michael P. Gallagher, Exelon, to NRC Document Control Desk, dated December 2, 2015, "10 CFR 54.21(b) Annual Amendment to the LaSalle County Station, Units 1 and 2, License Renewal Application (TAC Nos. MF5347 and MF5346)"
In Reference 1, Exelon Generation Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the LaSalle County Station (LSCS), Units 1 and 2. Reference 2 provided the first annual amendment to the LRA, as required by 10 CFR 54.21 (b).
Exelon has completed a review to identify any current licensing basis (CLB) changes made since submittal of the Reference 2 letter, which have a material effect on the content of the LRA, including the FSAR Supplement. This amendment identifies two (2) changes to the CLB that are considered to materially affect the contents of the LSCS LRA. Enclosure A contains a description of these CLB changes. Enclosure B contains updates to sections of the LRA affected by the changes.
June 8, 2016 U.S. Nuclear Regulatory Commission Page 2 This submittal satisfies the requirement within 10 CFR 54.21 (b) to submit an amendment addressing any such changes at least three months before scheduled completion of NRC review of the LRA.
There are no new or revised regulatory commitments contained in this letter.
If you have any questions, please contact Mr. John Hufnagel, Licensing Lead, LaSalle License Renewal Project, at 610-765-5829.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on ~6 -OS - 2':>/(
Respectfully,
~~
Vice President - License Renewal Projects Exelon Generation Company, LLC
Enclosures:
A. Description of CLB Changes that Impact the LRA Associated with the Second 10 CFR 54.21 (b) Annual Amendment B. LSCS LRA Updates Resulting from CLB Changes Identified in the Second 10 CFR 54.21(b) Annual Amendment cc: Regional Administrator - NRC Region Ill NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager (Environmental Review), NRR-DLR NRC Project Manager, NRR-DORL- LaSalle County Station NRC Senior Resident Inspector, LaSalle County Station Illinois Emergency Management Agency - Division of Nuclear Safety
RS-16-128 Enclosure A Page 1 of 1 Enclosure A Description of CLB Changes that Impact the LRA Associated with the Second 10 CFR 54.21(b) Annual Amendment
- 1) Addition of Robust FLEX Storage Building (Building #22)
In response to NRC Order EA 12-049 for implementation of Flexible Coping Strategies (FLEX) for external events beyond the original plant design basis (BDBEE), an additional storage building was installed to house FLEX equipment at LSCS. The Robust FLEX Storage Building (Building #22) is a stand-alone, cast-in-place, reinforced concrete structure with a floating slab supported on concrete strip footings resting on soil. The building is located on the north portion of the LSCS site, outside of the plants main power block, north of the Independent Spent Fuel Storage Installation (ISFSI) pad.
Robust FLEX Storage Building (Building #22) is not in scope as it is nonsafety-related and is separated from safety-related systems, structures, and components such that the structures failure would not impact a safety-related function. This building has been included in the Miscellaneous Not In Scope Structures. LRA Table 2.2-1, Plant Level Scoping Results, Comment #1 is revised as shown in Enclosure B to add this building to the list of not in scope structures.
- 2) Replacement of Carbon Steel Vacuum Breakers with Stainless Steel Vacuum Breakers in the Unit 1 Reactor Core Isolation Cooling (RCIC) System A design change to the RCIC System was performed to replace carbon steel vacuum breakers with stainless steel vacuum breakers in the RCIC turbine exhaust piping. The carbon steel vacuum breakers were swing type check valves which required a significant amount of rework associated with failed local leak rate tests. The replacement stainless steel valves are piston in-line check valves which offer improved reliability over the original carbon steel swing check valves. LRA Table 3.2.2-3, Reactor Core Isolation Cooling System Summary of Aging Management Evaluation, is revised as shown in Enclosure B to include the environments of Air - Indoor Uncontrolled (External) and Condensation (Internal) for stainless steel valve bodies with a pressure boundary intended function. The associated aging effects and aging management line items are also identified.
RS-16-128 Enclosure B Page 1 of 3 Enclosure B LSCS LRA Updates Resulting from CLB Changes Identified in the Second 10 CFR 54.21(b) Annual Amendment
RS-16-128 Enclosure B Page 2 of 3 As a result of the response to NRC Order EA 12-049 (Item 1 of Enclosure A), LRA Table 2.2-1, Plant Level Scoping Results, Comment #1 starting on page 2.2-5, is revised as shown below.
Additions are shown in bolded italics.
- 1. The Miscellaneous Not In Scope Structures are nonsafety-related and provide support, shelter, and protection for personnel, stored materials, or nonsafety-related systems, structures, and components (SSCs) that do not perform an intended function for license renewal. These nonsafety-related structures are also separated from safety-related systems, structures, and components such that the structures failure would not impact a safety-related function. Therefore, the following structures are not within the scope of license renewal: Administration Building (also known as the South Service Building or New Service Building), Building #30 (Records Storage Vault or Records Storage Building), IDNS (Illinois Department of Nuclear Safety) Building, Project Management Field Office, Training Building, Maintenance Shop, Building #1 (contractor fab shop, radiological outage, equip storage), Road Maintenance Building, Weld Shop, Warehouse (Stores Warehouse), Warehouses 3 - 6, Contractor PreFab Shop, Shad Net Maintenance Building, In-Processing Facility, MAF (Main Access Facility), Security Checkpoint, Building #11 (TSC and Security Diesels), NAF (Old Permanent Gatehouse or Gatehouse), Sewage Treatment Plant, Water Softener Building (Building #41), MUDS (Makeup Demineralizer System) Trailers, Pump Houses: (Building #40), River Screen House, Lake Blowdown Outfall Structure, Transporter Building, Hazardous/Mixed Waste Storage Facility (Building #20), Radwaste Storage, Building #33, Filling Station, Station Heat Chiller Pad, Fish Hatchery, Robust FLEX Storage Building (Building #22),
Robust FLEX Storage Building (Building #23), and Commercial FLEX Storage Building (Building #24).
RS-16-128 Enclosure B Page 3 of 3 As a result of the replacement of the Unit 1 carbon steel RCIC turbine exhaust vacuum breakers with stainless steel vacuum breakers (Item 2 of Enclosure A), LRA Table 3.2.2-3, Reactor Core Isolation Cooling System Summary of Aging Management Evaluation starting on page 3.2-55, is revised as shown below. Additions are indicated with bolded italics.
Table 3.2.2-3 Reactor Core Isolation Cooling System (Continued)
Component Type Intended Function Material Environment Aging Effect Requiring Aging Management NUREG-1801 Table 1 Item Notes Management Programs Item Valve Body Pressure Boundary Stainless Steel Air - Indoor None None V.F.EP-18 3.2.1-63 A Uncontrolled (External)
Air - Outdoor (External) Cracking External Surfaces V.D2.EP-103 3.2.1-7 A Monitoring of Mechanical Components (B.2.1.24)
Loss of Material External Surfaces V.D2.EP-107 3.2.1-4 A Monitoring of Mechanical Components (B.2.1.24)
Condensation Loss of Material Inspection of Internal V.D2.EP-61 3.2.1-48 A (Internal) Surfaces in Miscellaneous Piping and Ducting Components (B.2.1.25)
Treated Water (Internal) Loss of Material One-Time Inspection V.D2.EP-73 3.2.1-17 A (B.2.1.21)
Water Chemistry (B.2.1.2) V.D2.EP-73 3.2.1-17 B