RS-14-135, 10 CFR 54.21(b) Annual Amendment to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application: Difference between revisions

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{{#Wiki_filter:M ichael P. Gallagher Vice President.
{{#Wiki_filter:Michael P. Gallagher Vice President. License Renewal Exelon Generation                                                 Exelon Nuclear 200 Exelon Way Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 RS-14-135 May 5, 2014 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
License Renewal Exelon Generation Exelon Nuclear 200 Exelon Way RS-14-135 May 5, 2014 Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 U.S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, DC 20555-0001  


==Subject:==
==Subject:==
10 CFR 54.21(b) Annual Amendment to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application


==Reference:==
==Reference:==
Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon) to NRC Document Control Desk, dated May 29, 2013, "Application for Renewed Operating Licenses."
In the Reference letter, Exelon Generation Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (BBS). As required by 10 CFR 54.21(b), a review has been performed to identify any current licensing basis (CLB) changes made since submittal of the LRA which have a material effect on the content of the LRA, including the FSAR Supplement. This amendment identified a change to the current licensing basis (CLB) that materially affects the contents of the BBS LRA.
Enclosure A contains a description of this LRA change. Enclosure B contains an update to the LRA associated with this change.
There are no new or revised regulatory commitments contained in this letter.
If you have any questions, please contact Mr. AI Fulvio, Manager, Exelon License Renewal, at 610-765-5936.


Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 10 CFR 54.21(b) Annual Amendment to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon) to NRC Document Control Desk, dated May 29, 2013, "Application for Renewed Operating Licenses." In the Reference letter, Exelon Generation Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (BBS). As required by 10 CFR 54.21(b), a review has been performed to identify any current licensing basis (CLB) changes made since submittal of the LRA which have a material effect on the content of the LRA, including the FSAR Supplement.
May 5, 2014 U.S. Nuclear Regulatory Commission Page 2 I declare under penalty of perjury that the foregoing is true and correct.
This amendment identified a change to the current licensing basis (CLB) that materially affects the contents of the BBS LRA. Enclosure A contains a description of this LRA change. Enclosure B contains an update to the LRA associated with this change. There are no new or revised regulatory commitments contained in this letter. If you have any questions, please contact Mr. AI Fulvio, Manager, Exelon License Renewal, at 610-765-5936.
Executed on     5-5""' 20/4 Respectfully,
May 5, 2014 U.S. Nuclear Regulatory Commission Page 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on 5-5""' 20/4 Respectfully,  


==Enclosures:==
==Enclosures:==
A. Description of LRA Update Associated with RWST Heaters B. LRA Updates Associated with RWST Heaters cc:    Regional Administrator- NRC Region Ill NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager (Environmental Review), NRR-DLR NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station NRC Project Manager, NRR-DORL-Braidwood and Byron Stations Illinois Emergency Management Agency - Division of Nuclear Safety


A. Description of LRA Update Associated with RWST Heaters B. LRA Updates Associated with RWST Heaters cc: Regional Administrator-NRC Region Ill NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager (Environmental Review), NRR-DLR NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station NRC Project Manager, NRR-DORL-Braidwood and Byron Stations Illinois Emergency Management Agency -Division of Nuclear Safety RS-14-135 Enclosure A Page 1 of 1 Enclosure A Description of LRA Update Associated with RWST Heaters Prior to submittal of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 License Renewal Application (LRA), Exelon had replaced the Byron Units 1 and 2 Refueling Water Storage Tank (RWST) electric heaters. The material was changed from a carbon steel shell to a stainless steel shell. At the time of LRA submittal, the Braidwood Units 1 and 2 still had the original RWST electric heaters with carbon steel shells and stainless steel flanges.
RS-14-135 Enclosure A Page 1 of 1 Enclosure A Description of LRA Update Associated with RWST Heaters Prior to submittal of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 License Renewal Application (LRA), Exelon had replaced the Byron Units 1 and 2 Refueling Water Storage Tank (RWST) electric heaters. The material was changed from a carbon steel shell to a stainless steel shell. At the time of LRA submittal, the Braidwood Units 1 and 2 still had the original RWST electric heaters with carbon steel shells and stainless steel flanges.
These material differences were appropriately identified in the LRA Safety Injection System aging management review line items. In June 2013 and November 2013, the carbon steel shells on Braidwood Units 1 and 2, respectively, were physically modified to stainless steel, such that the Braidwood heaters are now all stainless steel similar to the Byron electric heaters. Therefore, with this submittal, the aging management review line items for the carbon steel material on the RWST electric heaters are deleted from the Safety Injection System aging management review line items, as shown in Enclosure B. The stainless steel electric heaters aging management review line items in the LRA on page 3.2-49 are now applicable to the complete Braidwood heater assembly. Therefore, no additional aging management review line  
These material differences were appropriately identified in the LRA Safety Injection System aging management review line items. In June 2013 and November 2013, the carbon steel shells on Braidwood Units 1 and 2, respectively, were physically modified to stainless steel, such that the Braidwood heaters are now all stainless steel similar to the Byron electric heaters.
Therefore, with this submittal, the aging management review line items for the carbon steel material on the RWST electric heaters are deleted from the Safety Injection System aging management review line items, as shown in Enclosure B. The stainless steel electric heaters aging management review line items in the LRA on page 3.2-49 are now applicable to the complete Braidwood heater assembly. Therefore, no additional aging management review line items are necessary.


items are necessary.
RS-14-135 Enclosure B Page 1 of 1 Enclosure B LRA Updates Associated with RWST Heaters As a result of the LRA update associated with the Braidwood RWST heater replacement described in Enclosure A of this letter, LRA Table 3.2.2-4 on page 3.2-48 is revised as shown below. Deletions are shown with strikethroughs.
 
Table 3.2.2-4                                               Safety Injection System Component     Intended Function     Material         Environment       Aging Effect Requiring   Aging Management         NUREG-1801 Item Table 1 Item Notes Type                                                                      Management              Programs Accumulator   Pressure Boundary Carbon or Low Air with Borated Water       Loss of Material     Boric Acid Corrosion         V.D1.E-28       3.2.1-9     A Alloy Steel with  Leakage (External)                                  (B.2.1.4)
RS-14-135 Enclosure B Page 1 of 1 Enclosure B LRA Updates Associated with RWST Heaters As a result of the LRA update associated with the Braidwood RWST heater replacement described in Enclosure A of this letter , LRA Table 3.2.2-4 on page 3.2-48 is revised as shown below. Deletions are shown with strikethroughs. Table 3.2.2-4   Safety Injection System Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Programs NUREG-1801 ItemTable 1 Item Notes Accumulator                                     Pressure Boundary                                                   Carbon or Low Alloy Steel with Stainless Steel Cladding Air with Borated Water Leakage (External)                    Loss of Material                 Boric Acid Corrosion (B.2.1.4) V.D1.E-28 3.2.1-9 A External Surfaces Monitoring of Mechanical Components (B.2.1.23) V.E.E-44 3.2.1-40 A Treated Borated Water (Internal)                    Loss of Material                 One-Time Inspection (B.2.1.20) V.D1.EP-41 3.2.1-22 A Water Chemistry (B.2.1.2)V.D1.EP-41 3.2.1-22 A Bolting Mechanical Closure Carbon and Low Alloy Steel Bolting Air with Borated Water Leakage (External)                                      Loss of Material                 Boric Acid Corrosion (B.2.1.4) V.E.E-41 3.2.1-9 A Bolting Integrity (B.2.1.9)V.E.EP-70 3.2.1-13 A Loss of Preload Bolting Integrity (B.2.1.9)V.E.EP-69 3.2.1-15 A Stainless Steel Bolting                Air with Borated Water Leakage (External)                    Loss of Material Bolting Integrity (B.2.1.9)V.E.EP-70 3.2.1-13 A Loss of Preload Bolting Integrity (B.2.1.9)V.E.EP-69 3.2.1-15 A Electric Heaters (Refueling Water Storage Tank)             
Stainless Steel External Surfaces            V.E.E-44     3.2.1-40     A Cladding Monitoring of Mechanical Components (B.2.1.23)
 
Treated Borated Water     Loss of Material     One-Time Inspection         V.D1.EP-41     3.2.1-22     A (Internal)                                    (B.2.1.20)
Leakage Boundary
Water Chemistry (B.2.1.2)     V.D1.EP-41     3.2.1-22     A Bolting   Mechanical Closure Carbon and Low Air with Borated Water       Loss of Material     Boric Acid Corrosion         V.E.E-41       3.2.1-9     A Alloy Steel    Leakage (External)                                  (B.2.1.4)
 
Bolting Bolting Integrity (B.2.1.9)   V.E.EP-70     3.2.1-13     A Loss of Preload   Bolting Integrity (B.2.1.9)   V.E.EP-69     3.2.1-15     A Stainless Steel Air with Borated Water     Loss of Material   Bolting Integrity (B.2.1.9)   V.E.EP-70     3.2.1-13     A Bolting      Leakage (External)      Loss of Preload   Bolting Integrity (B.2.1.9)   V.E.EP-69     3.2.1-15     A Electric     Leakage Boundary Carbon Steel - Air with Borated Water         Loss of Material     Boric Acid Corrosion         V.D1.E-28       3.2.1-9     A Heaters                        (Braidwood only) Leakage (External)                                      (B.2.1.4)
Carbon Steel  
(Refueling                                                                                        External Surfaces            V.E.E-44     3.2.1-40     A Water Storage                                                                                    Monitoring of Mechanical Tank)                                                                                          Components (B.2.1.23)
- (Braidwood only)
Treated Borated Water      Loss of Material     One-Time Inspection                                     G, 1 (Internal)                                    (B.2.1.20)
Air with Borated Water Leakage (External)
Water Chemistry (B.2.1.2)                                 G, 1}}
Loss of Material Boric Acid Corrosion (B.2.1.4) V.D1.E-28 3.2.1-9 A External Surfaces Monitoring of Mechanical Components (B.2.1.23)
V.E.E-44 3.2.1-40 A Treated Borated Water (Internal)
Loss of Material
 
One-Time Inspection (B.2.1.20)
G, 1 Water Chemistry (B.2.1.2) G, 1}}

Latest revision as of 06:03, 4 November 2019

10 CFR 54.21(b) Annual Amendment to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application
ML14125A300
Person / Time
Site: Byron, Braidwood  Constellation icon.png
Issue date: 05/05/2014
From: Gallagher M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-14-135
Download: ML14125A300 (4)
v • d • e


Text

Michael P. Gallagher Vice President. License Renewal Exelon Generation Exelon Nuclear 200 Exelon Way Kennett Square. PA 19348 610 765 5958 Office 610 765 5956 Fax www.exeloncorp.com michaelp.gallagher@exeloncorp.com 10 CFR 50 10 CFR 51 10 CFR 54 RS-14-135 May 5, 2014 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455

Subject:

10 CFR 54.21(b) Annual Amendment to the Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, License Renewal Application

Reference:

Letter from Michael P. Gallagher, Exelon Generation Company LLC (Exelon) to NRC Document Control Desk, dated May 29, 2013, "Application for Renewed Operating Licenses."

In the Reference letter, Exelon Generation Company, LLC (Exelon) submitted the License Renewal Application (LRA) for the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 (BBS). As required by 10 CFR 54.21(b), a review has been performed to identify any current licensing basis (CLB) changes made since submittal of the LRA which have a material effect on the content of the LRA, including the FSAR Supplement. This amendment identified a change to the current licensing basis (CLB) that materially affects the contents of the BBS LRA.

Enclosure A contains a description of this LRA change. Enclosure B contains an update to the LRA associated with this change.

There are no new or revised regulatory commitments contained in this letter.

If you have any questions, please contact Mr. AI Fulvio, Manager, Exelon License Renewal, at 610-765-5936.

May 5, 2014 U.S. Nuclear Regulatory Commission Page 2 I declare under penalty of perjury that the foregoing is true and correct.

Executed on 5-5""' 20/4 Respectfully,

Enclosures:

A. Description of LRA Update Associated with RWST Heaters B. LRA Updates Associated with RWST Heaters cc: Regional Administrator- NRC Region Ill NRC Project Manager (Safety Review), NRR-DLR NRC Project Manager (Environmental Review), NRR-DLR NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station NRC Project Manager, NRR-DORL-Braidwood and Byron Stations Illinois Emergency Management Agency - Division of Nuclear Safety

RS-14-135 Enclosure A Page 1 of 1 Enclosure A Description of LRA Update Associated with RWST Heaters Prior to submittal of the Byron Station, Units 1 and 2, and Braidwood Station, Units 1 and 2 License Renewal Application (LRA), Exelon had replaced the Byron Units 1 and 2 Refueling Water Storage Tank (RWST) electric heaters. The material was changed from a carbon steel shell to a stainless steel shell. At the time of LRA submittal, the Braidwood Units 1 and 2 still had the original RWST electric heaters with carbon steel shells and stainless steel flanges.

These material differences were appropriately identified in the LRA Safety Injection System aging management review line items. In June 2013 and November 2013, the carbon steel shells on Braidwood Units 1 and 2, respectively, were physically modified to stainless steel, such that the Braidwood heaters are now all stainless steel similar to the Byron electric heaters.

Therefore, with this submittal, the aging management review line items for the carbon steel material on the RWST electric heaters are deleted from the Safety Injection System aging management review line items, as shown in Enclosure B. The stainless steel electric heaters aging management review line items in the LRA on page 3.2-49 are now applicable to the complete Braidwood heater assembly. Therefore, no additional aging management review line items are necessary.

RS-14-135 Enclosure B Page 1 of 1 Enclosure B LRA Updates Associated with RWST Heaters As a result of the LRA update associated with the Braidwood RWST heater replacement described in Enclosure A of this letter, LRA Table 3.2.2-4 on page 3.2-48 is revised as shown below. Deletions are shown with strikethroughs.

Table 3.2.2-4 Safety Injection System Component Intended Function Material Environment Aging Effect Requiring Aging Management NUREG-1801 Item Table 1 Item Notes Type Management Programs Accumulator Pressure Boundary Carbon or Low Air with Borated Water Loss of Material Boric Acid Corrosion V.D1.E-28 3.2.1-9 A Alloy Steel with Leakage (External) (B.2.1.4)

Stainless Steel External Surfaces V.E.E-44 3.2.1-40 A Cladding Monitoring of Mechanical Components (B.2.1.23)

Treated Borated Water Loss of Material One-Time Inspection V.D1.EP-41 3.2.1-22 A (Internal) (B.2.1.20)

Water Chemistry (B.2.1.2) V.D1.EP-41 3.2.1-22 A Bolting Mechanical Closure Carbon and Low Air with Borated Water Loss of Material Boric Acid Corrosion V.E.E-41 3.2.1-9 A Alloy Steel Leakage (External) (B.2.1.4)

Bolting Bolting Integrity (B.2.1.9) V.E.EP-70 3.2.1-13 A Loss of Preload Bolting Integrity (B.2.1.9) V.E.EP-69 3.2.1-15 A Stainless Steel Air with Borated Water Loss of Material Bolting Integrity (B.2.1.9) V.E.EP-70 3.2.1-13 A Bolting Leakage (External) Loss of Preload Bolting Integrity (B.2.1.9) V.E.EP-69 3.2.1-15 A Electric Leakage Boundary Carbon Steel - Air with Borated Water Loss of Material Boric Acid Corrosion V.D1.E-28 3.2.1-9 A Heaters (Braidwood only) Leakage (External) (B.2.1.4)

(Refueling External Surfaces V.E.E-44 3.2.1-40 A Water Storage Monitoring of Mechanical Tank) Components (B.2.1.23)

Treated Borated Water Loss of Material One-Time Inspection G, 1 (Internal) (B.2.1.20)

Water Chemistry (B.2.1.2) G, 1

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