ML050600274
| ML050600274 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/28/2005 |
| From: | Abney T Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TAC MC1704, TAC MC1705, TAC MC1706 | |
| Download: ML050600274 (33) | |
Text
February 28, 2005 10 CFR 54 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:
In the Matter of
) Docket Nos. 50-259 Tennessee Valley Authority
) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA) - LRA SECTION 2.1 FINAL STATUS OF RESPONSE TO RAI 2.1-2, A.3 (TAC NOS. MC1704, MC1705, AND MC1706)
By letter dated December 31, 2003, TVA submitted, for NRC review, an application pursuant to 10 CFR 54, to renew the operating licenses for the Browns Ferry Nuclear Plant, Units 1, 2, and 3. The status of this RAIs methodology and progress was provided in a January 31, 2005 TVA response letter. The subject RAI 2.1-2, A.3 is the review of seismic class I piping boundaries to identify additional piping segments and supports/equivalent anchors that need to be placed in the scope of license renewal.
The enclosures to this letter contain the final status information and results from the calculation review requested by the NRC.
U.S. Nuclear Regulatory Commission Page 2 February 28, 2005 If you have any questions regarding this information, please contact Ken Brune, Browns Ferry License Renewal Project Manager, at (423) 751-8421.
I declare under penalty of perjury that the foregoing is true and correct. Executed on this 28th day of February, 2005.
Sincerely, Original Signed by:
T. E. Abney Manager of Licensing and Industry Affairs
Enclosure:
cc: See page 3
U.S. Nuclear Regulatory Commission Page 3 February 28, 2005 Enclosure cc (Enclosures):
State Health Officer Alabama Department of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, Alabama 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, Alabama 35611 (Via NRC Electronic Distribution)
Enclosures cc (Enclosures):
U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 NRC Unit 1 Restart Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, Alabama 35611-6970 cc: continued page 4
U.S. Nuclear Regulatory Commission Page 4 February 28, 2005 cc: (Enclosures)
Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Yoira K. Diaz-Sanabria, Project Manager U.S. Nuclear Regulatory Commission (MS 011F1)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Ramachandran Subbaratnam, Project Manager U.S. Nuclear Regulatory Commission (MS 011F1)
One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739
U.S. Nuclear Regulatory Commission Page 5 February 28, 2005 GLS:BAB Enclosure cc (Enclosures):
A. S. Bhatnagar, LP 6-C K. A. Brune, LP 4F-C J. C. Fornicola, LP 6A-C R. G. Jones, NAB 1A-BFN K. L. Krueger, POB 2C-BFN R. F. Marks, Jr., PAB 1A-BFN F. C. Mashburn, BR 4X-C N. M. Moon, LP 6A-C J. R. Rupert, NAB 1F-BFN K. W. Singer, LP 6A-C M. D. Skaggs, PAB 1E-BFN E. J. Vigluicci, ET 11A-K NSRB Support, LP 5M-C EDMS, WT CA-K s://Licensing/Lic/BFN LR Final Status of RAI 2.1-2, A.3 TVA Response Letter.doc
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA),
FINAL RESPONSE TO RAI 2.1-2, A.3 (SEE ATTACHED)
E1 - 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA),
FINAL RESPONSE TO RAI 2.1-2, A.3 By letter dated December 31, 2003, TVA submitted, for NRC review, an application pursuant to 10 CFR 54, to renew the operating licenses for the Browns Ferry Nuclear Plant, Units 1, 2, and 3. The status of this RAIs methodology and progress was provided in a January 31, 2005 TVA response letter.
The subject RAI 2.1-2, A.3 is the review of seismic class I piping boundaries to identify additional piping segments and supports/equivalent anchors that need to be placed in the scope of license renewal.
Listed below in Enclosure 1 is the final summary of information found. Enclosures 2 and 3 provides additional discussion and changes to the boundary drawings and the LRA for the affected mechanical systems and structures.
FINAL RESPONSE TO NRC RAI 2.1-2, A.3:
TVA has performed a detailed review of the seismic class I qualification documentation to identify the non-safety related piping, supports/equivalent anchors, or other components that are within the scope of license renewal for 54.4(a)(2) for the cases where non-safety related piping or components are directly connected to safety related piping or components. The seismic class I qualification used for this review complies with the requirements of IE Bulletin 79-14.
The following is a summary of changes required to the LRA and boundaries as a result of the review:
The following mechanical systems had additional piping or components added to scope. For these systems boundary changes were required to include additional piping and components but no changes to the LRA were required since the component / material
/ environment / program combination was already addressed in the LRA.
- Condensate and Demineralized Water System (002)
- Standby Liquid Control System (063) - Additional piping was added to scope.
E1 - 2
- Containment System (064) - Additional piping was added to scope.
- Reactor Building Closed Cooling Water System (070)
- Auxiliary Decay Heat Removal System (072)
- Fuel Pool Cooling and Cleanup System (078)
The following mechanical systems had additional piping or components added to scope. For these systems boundary changes were required to include additional piping and components and changes to the LRA were required since the component /material
/environment /program combination was not addressed in the LRA.
- CO2 System (039) - Four new Aging Management Review (AMR) line items were added to the LRA.
provides additional details on the boundary and LRA changes for the Mechanical Systems. As a result of the review, the following two structures were added to scope:
- The Radwaste Building contains CO2 piping (System 39) and a safety related drain line (System 77) that are in scope for license renewal. The CO2 piping is required to support fire protection requirements (10 CFR 50.48) based on the criterion of 10 CFR 54.4 (a)(3) and 10 CFR 54.4 (a)(1).
The safety related drain line is from the Standby Gas Treatment system to a off-gas condensate sump in the Radwaste Building and is in the scope of license renewal based on the criterion of 10 CFR 54.4 (a)(1). Only those rooms of the Radwaste Building that contain the fire protection piping or the Standby Gas Treatment drain line are required to provide structural support and shelter/protection to support the intended function of the piping.
- The Service Building contains CO2 lines (System 39) and a liquid (water) filled line for the fire protection system (System 26) that are required to support fire protection
E1 - 3 requirements (10CFR 50.48) based on the criterion of 10 CFR 54.4 (a)(3). Only those rooms of the Service Building that contain the fire protection piping are required to provide structural support and shelter/protection to support the intended function of the fire protection piping.
provides additional details on the LRA changes for the Structures.
ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA),
FINAL RESPONSE TO RAI 2.1-2, A.3 (SEE ATTACHED)
ENCLOSURE 2 MECHANICAL SYSTEMS E2 - 1 This enclosure provides the additional details for the mechanical systems which had additional piping or components added to scope as a result of the review.
Condensate and Demineralized Water System (002)
Additional piping and components were added to scope in the Radwaste Building. The piping and components are in the Cleanup Decant Pump Room of the Radwaste Building and are shown on drawing 0-47E856-1-LR at coordinate K9. The component/material/environment combinations for the added scope are already addressed in the LRA. No changes to the System 002 portion of the LRA are required.
CO2 System (039)
Additional piping and components were added to scope. Vent lines on drawings 0-47E843-1-LR at coordinates B3 and C3, 4, & 5 and 3-47E843-2-LR at coordinates F6 and G6, 7 & 8 were added to scope. Also, review of the Seismic Class I analysis boundaries identified portions of the CO2 System which had Safety-Related functions which were not previously identified.
The addition of the vent lines and the additional Safety-Related functions requires the following changes to the LRA:
The (a)(1) and (a)(2) blocks in table on page 2.3-60 should be shown Yes instead of No as shown below:
(a)(1)
(a)(2)
(a)(3) FP (a)(3) EQ (a)(3) ATWS (a)(3) SBO Yes Yes Yes No No No Add the following to the CO2 System intended functions on Page 2.3-60:
Portions of the CO2 system are designed not to inadvertently initiate during a shutdown after the applicable design basis events. Release of CO2 into the control bay would adversely affect manual operation of equipment and habitability in the protected rooms as well as cause temperature buildup due to Heating, Ventilating, and Air Conditioning System isolation. Release of CO2 into the diesel generator compartments would cause sealing of the compartments and possible consequent overheating of the diesel generators because of inadequate ventilation.
Add outside air as environment on page 3.3-22.
Add a flexible connector to the component types in Table 2.3.3.12 on page 2.3-61 as shown below.
Table 2.3.3.12 CO2 System Component Type Intended Functions Flexible Connectors PB Add the following lines to Table 3.3.2.12 as shown below.
E2 - 2 Table 3.3.2.12: CO2 System (039) - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG
-1801 Vol. 2 Item Table 1 Item Notes Flexible Connectors PB Elastomer (Fabric Reinforced Rubber)
Inside Air (external)
Elastomer degradation due to ultraviolet radiation.
Fire Protection Program VII.I.1-b None F, 2 Flexible Connectors PB Elastomer (Fabric Reinforced Rubber)
Air/gas (internal)
None None None None J, 6 Fittings PB Carbon and Low Alloy Steel Outside Air (external)
Loss of material due to general corrosion.
Fire Protection Program VII.I.1-b 3.3.1.5 A
Piping PB Carbon and Low Alloy Steel Outside Air (external)
Loss of material due to general corrosion.
Fire Protection Program VII.I.1-b 3.3.1.5 A
Sampling and Water Quality System (043)
Additional components were added to scope. The components are Grab Sample Boxes which were credited as anchorage in the seismic analysis. The Grab Sample Boxes are shown on drawings 1-47E610-43-1-LR at coordinate D8, 2-47E610-43-1-LR at coordinate D8, and 3-47E610-43-6-LR at coordinate G8.
The addition of the Grab Sample Box requires the following changes to the LRA:
Add the following line in the Application on page 2.3-66.
Table 2.3.3.12 Sampling and Water Quality System Component Type Intended Functions Panel SS Add the following line to Table 3.3.2.14.
Table 3.3.2.14: Sampling and Water Quality System (043) - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-1801 Vol.
2 Item Table 1 Item Notes Panel (Open sample panel)
SS Carbon and Low Alloy Steel Inside Air (external)
Loss of material due to general corrosion.
System Monitoring Program (B.2.1.39)
V.E.1-b 3.2.1.10 C
E2 - 3 Standby Liquid Control System (063)
Additional piping and components were added to scope. The piping and components are downstream of valve SHV-539 and are shown on drawing 2-47E854-1-LR at coordinate D7. The component/material/environment combinations for the added scope are already addressed in the LRA. No changes to the System 063 portion of the LRA are required.
Containment System (064)
Additional piping and components were added to scope.
Tubing was added to scope on new Boundary Drawings 2-47E610-64-3-LR at coordinates A4 and B4 and 3-47E610-64-3-LR at coordinates B4 and C4. The component/material/environment combinations for the added scope are already addressed in the LRA. No changes to the System 064 tables of the LRA are required.
The addition of the tubing requires the following change to the LRA:
Add drawings 2-47E610-64-3-LR and 3-47E610-64-3-LR to License Renewal Drawing list on page 2.3-18.
Off-Gas System (066)
Additional piping and components were added to scope. The additional piping and components are drain lines in the Cleanup Decant Pump Room in the Radwaste Building. The drain lines are shown on drawings 1-47E809-2-LR at coordinate F5, 2-47E809-2 at coordinate F5, 3-47E809-2-LR at coordinate F5 and 0-47E830-1-LR at coordinate F8.
The addition of the drain lines requires the following changes to the LRA:
The (a)(2) block in table on page 2.3-75 should be shown Yes instead of no as shown below (a)(1)
(a)(2)
(a)(3) FP (a)(3) EQ (a)(3) ATWS (a)(3) SBO Yes Yes No No No No Add new drawings 1-47E809-3-LR, 2-47E809-3-LR, & 3-47E809-3-LR to License Renewal Drawings on page 2.3-75.
Add the following line in Table 2.3.3.19 on page 2.3-76:
Table 2.3.3.19 Off-Gas System Component Type Intended Functions Valves PB
E2 - 4 Add the following lines in Table 3.3.2.19 on page 3.3-185:
Table 3.3.2.19: Off-Gas System (066) - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG
-1801 Vol. 2 Item Table 1 Item Notes Valves PB Carbon and Low Alloy Steel Air/gas (internal)
Loss of material due to general corrosion.
One-Time Inspection Program (B.2.1.29)
V.B.1-a 3.2.1.3 C
Valves PB Carbon and Low Alloy Steel Inside Air (external)
Loss of material due to general corrosion.
Systems Monitoring Program (B.2.1.39)
V.E.1-b 3.2.1.10 A
Reactor Building Closed Cooling Water System (070)
Additional piping was added to scope. The additional piping in the Isolation Valve Pit Building and is shown on drawing 3-47E822-1-LR at coordinates E4 and F4. The component/material/
environment combinations for the added scope are already addressed in the LRA. No changes to the System 070 portion of the LRA are required.
Auxiliary Decay Heat Removal System (072)
Additional components were added to scope. The components added are the shells of the heat exchangers which are the first anchors after the Seismic Class I boundary. The heat exchangers are shown on drawing 0-47E873-1-LR at coordinates D8 and G8. The component/material/environment combinations for the added scope are already addressed in the LRA. No changes to the System 072 portion of the LRA are required.
Radioactive Waste Treatment System (077)
Additional piping and components were added to scope in the Cleanup Decant Pump Room in the Radwaste Building. The piping and components are shown on drawings 0-47E830-1-LR at coordinates G6, 7, & 8 and H6, 7 & 8, 0-47830-2-LR at coordinates C6, G4, G6 and H6, 0-47E830-5-LR coordinates A3, 5, & 7, B3, 5, & 7, and C3, 5, & 7, and 0-47E830-6-LR at coordinate F5.
Notes were added to drawings 1-47E852-1-LR, 1-47E852-2-LR, 2-47E852-1-LR, 2-47E852-2-LR, 3-47E852-1-LR and 3-47E852-2-LR. These notes clarify that embedded piping is in scope for anchorage when attached to non-embedded in scope piping and that all piping between the embedded piping and in scope non-embedded piping is in scope.
The additional piping and components requires the following changes to the LRA:
Add Drawings 0-47830-2-LR and 0-47E830-6-LR to License Renewal drawings on page 2.3-90 of the Application. Cleanup Decant Pump Room in the Radwaste Building Add the following lines to Table 3.3.2.25 in the Application as shown below
E2 - 5 Table 3.3.2.25:
Radioactive Waste Treatment System (077) - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-1801 Vol.
2 Item Table 1 Item Notes Fittings PB Aluminum Alloy Treated Water (internal)
Crack initiation/growth due to SCC.
Chemistry Control Program (B.2.1.5)
One-Time Inspection Program (B.2.1.29)
V.C.1-a None F, 3 Fittings PB Aluminum Alloy Treated Water (internal)
Loss of material due to crevice and pitting corrosion.
Chemistry Control Program (B.2.1.5)
One-Time Inspection Program (B.2.1.29)
V.C.1-a None F, 3, Fittings PB Aluminum Alloy Inside Air (external)
None None V.E.1-b None F, 2 Fittings PB Copper Alloy (Bronze)
Treated Water Loss of material due to crevice and pitting corrosion One-Time Inspection Program V.C.1-a None F,3 Fittings PB Copper Alloy (Bronze)
Treated Water Loss of material due to selective leaching Selective Leaching of Materials Program V.C.1-a None F,3 Fittings PB Copper Alloy (Bronze)
Inside Air None None V.E.1-b None F,2 Piping PB Aluminum Alloy Treated Water (internal)
Crack initiation/growth due to SCC.
Chemistry Control Program (B.2.1.5)
One-Time Inspection Program (B.2.1.29)
V.C.1-a None F, 3 Piping PB Aluminum Alloy Treated Water (internal)
Loss of material due to crevice and pitting corrosion.
Chemistry Control Program (B.2.1.5)
One-Time Inspection Program (B.2.1.29)
V.C.1-a None F, 3, Piping PB Aluminum Alloy Inside Air (external)
None None V.E.1-b None F, 2
E2 - 6 Table 3.3.2.25:
Radioactive Waste Treatment System (077) - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG-1801 Vol.
2 Item Table 1 Item Notes Pumps PB Stainless Steel Treated Water Loss of material due to crevice and pitting corrosion One-Time Inspection Program V.C.1-b 3.2.1.5 C
Pumps PB Stainless Steel Inside Air None None V.E.1-b None F,2 Strainers PB Cast Iron and Cast Iron Alloy Treated Water Loss of material due to general, crevice, and pitting corrosion One-Time Inspection Program None None J,3 Strainers PB Cast Iron and Cast Iron Alloy Treated Water Loss of material due to selective leaching Selective Leaching of Materials Program None None J,3 Strainers PB Cast Iron and Cast Iron Alloy Inside Air Loss of material due to general corrosion System Monitoring Program V.E.1-b None F,3 Fuel Pool Cooling and Cleanup System (078)
Additional piping and components were added to scope. The piping and components added to scope are in the Ventilation Equipment Room in the Radwaste Building. They are shown on drawings 0-47E832-1-LR at coordinate C5, 1-47E832-1-LR at coordinate I9, 2-47E832-1-LR at coordinate B3, and 3-47E832-1-LR at coordinate I4. The component/material/ environment combinations for the added scope are already addressed in the LRA. No changes to the System 078 tables of the LRA are required.
The additional piping and components requires the following change to the LRA:
Add Drawings 0-47E832-1-LR, 1-47E832-1-LR, 2-47E832-1-LR, and 3-47E832-1-LR to License Renewal drawings on page 2.3-92.
Diesel Generator Starting Air System (086)
Additional piping and components were added to scope. The piping and components added to scope are associated with the outlet filter of the Air Dryer Skid which is credited as an anchor in the seismic analysis. The additional in scope piping and components are shown on Drawings 0-47E861-1-LR at coordinate C4 & C6, 0-47E861-2-LR at coordinate D4 & D6, 0-47E861-3-LR at coordinate C4 & C6, 0-47E861-4-LR at coordinate C4 & C6, 3-47E861-1-LR at coordinate C4 & C6, 3-47E861-2-LR at coordinate C4 & C6, 3-47E861-3-LR at coordinate C4 & C6, and 3-47E861-4-LR at coordinate C4 & C6.
The additional piping and components requires the following changes to the LRA:
E2 - 7 Revise Table 3.3.2.30 in the Application as shown below.
Table 3.3.2.30: Diesel Generator Starting Air System (086) - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging effect requiring management Aging Management Program NUREG -
1801 Vol.
2 Item Table 1 Item Notes Strainers PB Stainless Steel Air/gas (internal)
None None VII.H2.2-a None F, 3 Strainers PB Stainless Steel Inside Air (external)
None None VII.I.1-b None J, 3
ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1, 2, AND 3 LICENSE RENEWAL APPLICATION (LRA),
FINAL RESPONSE TO RAI 2.1-2, A.3 (SEE ATTACHED)
ENCLOSURE 3 STRUCTURES E3 - 1 This enclosure provides the additional details for buildings which were added to scope as a result of the review.
The Radwaste and Service Buildings were added to scope as a result of the review and the LRA changes as shown below:
In Table 2.2.2, Structures Scoping Results, In-Scope should be changed Yes for the Radwaste and Service Building on Page 2.2-11.
Add 2.4.7.8 Radwaste Building and 2.4.7.9 Service Building to the Section 2.4 Table on page 2.4-3 for the Non-Class 1 Structures.
Add 2.4.7.8 Radwaste Building and 2.4.7.9 Service Building to the Section 3.5.1 Table on page 3.5-2 for the Non-Class 1 Structures.
Add 3.5.2.29 Radwaste Building and 3.5.2.30 Service Building to the Section 3.5.2 Table on page 3.5-3 for the Non-Class 1 Structures.
Add 3.5.2.1.29 Radwaste Building and 3.5.2.1.30 Service Building to the Section 3.5.2 Table on page 3.5-5 for the Non-Class 1 Structures.
In Section 2.4.8.1, Structures and Component Supports Commodity Group, revise the first paragraph to read:
This group includes specific types of structure and component support elements located within and attached to the exterior of in-scope structures.
Drawing 0-10E201-01-LR includes the Service and Radwaste Buildings in scope.
E3 - 2 Add the following Sections in the Application for structures as shown below:
2.4.7.8 Radwaste Building Description The Radwaste Building is a cellular box-type concrete structure extending approximately 20 feet below grade and 30 feet above grade and is supported by steel H-piles driven to bedrock. This building houses common services to all three units. This building is comprised predominantly of thick walls and slabs, the dimensions of which are determined by shielding requirements. In a few instances, walls and slabs are determined by structural requirements. The roof system is a steel framed structure with either bracket supports on concrete walls or steel columns supported by the concrete floor at El. 580.0.
The Radwaste Building contains CO2 piping and a safety related drain line that are in-scope for license renewal. The CO2 piping is required to support fire protection requirements (10 CFR 50.48) based on the criterion of 10 CFR 54.4 (a)(3) and 54.4(a)(1). The safety related drain line is from the Standby Gas Treatment system to a radwaste sump in the Radwaste Building and is in the scope of license renewal based on the criterion of 10 CFR 54.4 (a)(1). Only those rooms of the Radwaste Building that contain the fire protection piping or the Standby Gas Treatment drain line are required to provide structural support and shelter/protection to support the intended function of the piping.
The Radwaste Building provides:
Structural support and shelter/protection for components required for safe shutdown following fires.
Structural support and shelter/protection for safety-related components.
The Radwaste Building is in the scope of 10 CFR 54 because it meets the following criteria of 10 CFR 54.4.
(a)(1)
(a)(2)
(a)(3) FP (a)(3) EQ (a)(3) ATWS (a)(3) SBO No Yes Yes No No No The Radwaste Building intended functions are:
Provides structural support and shelter/protection for components relied upon to demonstrate compliance with the FP regulated event Provides structural support and shelter/protection for safety-related components The portions of the Radwaste Building that contain components requiring an AMR include the entire structure and the component supports detailed below for the rooms that contain the in-scope piping systems discussed above.
The following rooms contain the piping within the scope of license renewal: (10 CFR 50.48 and 10 CFR 54.4(a)):
Radwaste Ventilation Equipment Rm 580.0-64 on elevation 580.0 (contains CO2 fire protection piping within the seismic class I boundary in scope for 54.4(a)(1) and
E3 - 3 54.4(a)(3) and where the seismic boundary terminates at an anchor the remaining piping is in scope for 54.4(a)(3) [50.48] for pressure boundary only Power Stores Rm 580.0-62 on elevation 580.0 (contains CO2 fire protection 54.4(a)(3)
[50.48] piping for pressure boundary only)
Fan Room Rm 580.0-63 on elevation 580.0 (contains CO2 fire protection 54.4(a)(3)
[50.48] piping for pressure boundary only)
The pipe supports for the CO2 fire protection piping in the Radwaste Ventilation Equipment Room are within the scope of license renewal (LR) and all other pipe supports for other system piping located in this room are included in-scope for LR. Only the pipe supports for the CO2 fire protection piping in the Power Stores room and Radwaste Fan Room are within the scope of license renewal (LR). These supports are scoped and screened in LRA section 2.4.8 and are included with commodity group Non-ASME Equivalent Supports and Components. The AMR evaluation is in LRA section 3.5.1.26.
The following room contains the piping for the safety-related [54.4(a)(1)] drain line from the Standby Gas Treatment system to a sump in the Radwaste Building:
Cleanup Decant Pump Rm 546.0-3 on elevation 546.0 The pipe supports for the safety-related drain line from the Standby Gas Treatment system located in this room are in-scope for LR and all other pipe supports for other system piping located in this room are included in-scope for LR. These supports are scoped and screened in LRA section 2.4.8 and are included with commodity group Non-ASME Equivalent Supports and Components. The AMR evaluation is in LRA section 3.5.1.26.
UFSAR References Additional details for the Radwaste Building structure are found in UFSAR 12.2.5 and F.6.14.
License Renewal Drawings The license renewal drawing for the Radwaste Building is listed below.
0-10E201-01-LR Components Subject to AMR The component types that require aging management review are indicated in Table 2.4.7.8, Radwaste Building.
The aging management review results for these component types are provided in Table 3.5.2.29, Radwaste Building - Summary of Aging Management Evaluation.
E3 - 4 Table 2.4.7.8 Radwaste Building Component Type Intended Functions Masonry Block SS(NSR)
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Roof Membrane SP Structural Steel Beams, Columns, Plates, and Trusses SS(NSR)
E3 - 5 3.5.2.1.29 Radwaste Building Materials The materials of construction for Radwaste Building components are:
Carbon and low alloy steel Masonry block Reinforced concrete Roof Membrane (Insulation, flashing, sealants and wood nailers)
Environment Radwaste Building components are exposed to the following environments:
Buried Inside air Outside air Aging Effects Requiring Management The following aging effects associated with the Radwaste Building require management:
Cracking, loss of bond, loss of material (spalling, scaling) due to corrosion of embedded steel Cracks due to restraint, shrinkage, creep, aggressive environment Expansion and cracking due to reaction with aggregates Increase in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack Increase in porosity and permeability, loss of strength due to leaching of calcium hydroxide Loss of material (spalling, scaling) and cracking due to freeze-thaw Loss of material due to general corrosion Loss of weatherproofing integrity due to shrinkage, cracking, drying, separation, organic decomposition, wear, weathering Aging Management Programs The following aging management programs manage the aging effects for Radwaste Building components.
Masonry Wall Program (B.2.1.35)
Structures Monitoring Program (B.2.1.36)
E3 - 6 Table 3.5.2.29:
Radwaste Building - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG -
1801 Vol. 2 Item Table 1 Item Notes Masonry Block SS(NSR)
Masonry Inside Air Cracking due to restraint, shrinkage, creep, aggressive environment Masonry Wall Program (B.2.1.35)
III.A3.3-a 3.5.1.24 A
Carbon and Low Alloy Steel Inside Air Loss of material due to general corrosion.
Structures Monitoring Program (B.2.1.36)
III.A3.2-a 3.5.1.20 A
Carbon and Low Alloy Steel Buried None None III.A3.2-a None I, 4 Piles SS(NSR)
Carbon and Low Alloy Steel Embedded/encased None None III.A3.2-a None I, 3 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried Loss of material (spalling, scaling) and cracking due to freeze-thaw.
Structures Monitoring Program (B.2.1.36)
III.A3.1-a 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-b None I, 5 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-c None I, 6 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-e None I, 7 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-g None I, 8 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-h None I, 1 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air Expansion and cracking due to reaction with aggregates.
Structures Monitoring Program (B.2.1.36)
III.A3.1-c 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air Cracking, loss of bond, loss of material (spalling, scaling) due to corrosion of embedded steel.
Structures Monitoring Program (B.2.1.36)
III.A3.1-d 3.5.1.20 A
E3 - 7 Table 3.5.2.29:
Radwaste Building - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG -
1801 Vol. 2 Item Table 1 Item Notes Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air Increase in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack.
Structures Monitoring Program (B.2.1.36)
III.A3.1-f 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air None None III.A3.1-h None I, 1 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air None None III.A3.1-j None I, 2 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Loss of material (spalling, scaling) and cracking due to freeze-thaw.
Structures Monitoring Program (B.2.1.36)
III.A3.1-a 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Increase in porosity and permeability, loss of strength due to leaching of calcium hydroxide.
Structures Monitoring Program (B.2.1.36)
III.A3.1-b 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Expansion and cracking due to reaction with aggregates.
Structures Monitoring Program (B.2.1.36)
III.A3.1-c 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Cracking, loss of bond, loss of material (spalling, scaling) due to corrosion of embedded steel.
Structures Monitoring Program (B.2.1.36)
III.A3.1-d 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Increase in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack.
Structures Monitoring Program (B.2.1.36)
III.A3.1-f 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air None None III.A3.1-h None I, 1 Roof Membrane SP Roof Membrane Outside Air Loss of weatherproofing integrity due to cracking, drying, organic decomposition, separation, shrinkage, wear, weathering.
Structures Monitoring Program (B.2.1.36)
None None J, 9 Structural Steel Beams, Columns, Plates, Trusses SS(NSR)
Carbon and Low Alloy Steel Inside Air Loss of material due to general corrosion.
Structures Monitoring Program (B.2.1.36)
III.A3.2-a 3.5.1.20 A
E3 - 8 Table Notes:
Industry Standard Notes:
Note A Consistent with NUREG-1801 item for component, material, environment, and aging effect. The AMP is consistent with NUREG-1801.
Note I Aging effect in NUREG-1801 item for this component, material and environment combination is not applicable.
Note J Neither the component nor the material and environment combination is evaluated in NUREG-1801.
Plant Specific Notes:
1 Cracks, distortion, increase in component stress level due to settlement are not aging effects requiring management for structures founded on rock or bearing piles. See further evaluation in Section 3.5.2.2.2.1.
2 Conditional requirements for elevated temperature are satisfied. Therefore, a plant specific aging management program is not required. See further evaluation in Section 3.5.2.2.2.1.
3 There are no applicable aging effects for this material/environment combination. This is consistent with industry guidance.
4 NUREG 1557 Table B9 states that steel piles driven in undisturbed soil have been unaffected by corrosion and those driven in disturbed soil experience minor to moderate corrosion to a small area of metal. This is a non-significant aging effect that does not require aging management.
5 For increase in porosity and permeability, loss of strength due to leaching of calcium hydroxide of concrete in inaccessible areas, no plant specific aging management is required. See further evaluation in Section 3.5.2.2.2.1.
6 For expansion and cracking due to reaction with aggregates of concrete in inaccessible areas, no aging management is required. See further evaluation in Section 3.5.2.2.2.1.
7 For cracking, loss of bond, loss of material (spalling, scaling) due to corrosion of embedded steel in concrete for inaccessible areas, no plant specific aging management is required. See further evaluation in Section 3.5.2.2.2.2.
8 For increase in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack of concrete for inaccessible areas, no plant specific aging management is required. See further evaluation in Section 3.5.2.2.2.2.
9 The aging effects and AMP identified for this material/environment combination are consistent with industry guidance.
E3 - 9 2.4.7.9 Service Building Description This structure consists of exterior concrete walls and footings with an interior structural steel frame supported by concrete footings. Concrete floor slabs are used. The building provides office space and shop areas for various on-site organizations.
The Service Building contains CO2 piping and a liquid (water) filled piping for the fire protection system that are required to support fire protection requirements (10CFR 50.48) based on the criterion of 10 CFR 54.4 (a)(3). Only those rooms of the Service Building that contain the fire protection piping are required to provide structural support and shelter/protection to support the intended function of the fire protection piping.
The Service Building provides:
Structural support and shelter/protection for components required for safe shutdown following fires.
The Service Building is in the scope of 10 CFR 54 because it meets the following criteria of 10 CFR 54.4.
(a)(1)
(a)(2)
(a)(3) FP (a)(3) EQ (a)(3) ATWS (a)(3) SBO No No Yes No No No The Service Building intended function is:
Provides structural support and shelter/protection for components relied upon to demonstrate compliance with the FP regulated event.
The portions of the Service Building that contain components requiring an AMR are as described below:
Two CO2 fire protection piping lines enter the Service Building from the Radwaste Building between column lines S6 and S7 in the west to east direction of the Service Building (approximately 5 feet west of column line S7) at elevation 590.0 and is routed north between column lines Wa of the Radwaste Building and Sa of the Service Building. The piping is then routed west just north of column line Sa between column lines S7 and S6 in the east to west direction for approximately 7 feet and drops down through the floor slab at elevation 580.0 of the Service Building to approximately elevation 577.0 for one line and elevation 576.0 for the other line. The piping at elevation 576.0 continues to run approximately 4.5 feet in the west direction towards column line S6 and then is routed north between column lines Sa and Sf of the Service Building in the south to north direction and terminates at a LR boundary valve. The piping at elevation 577.0 continues to run approximately 9.5 feet in the west direction towards column line S6 (approximately 2 feet west of column line S6) and then is routed north for approximately 10 feet between column lines Sa and Sb of the Service Building and terminates with an end cap on the line. Additionally, there is a water filled fire protection line that enters the Service Building from the unit 1 Turbine Building at approximately 4.5 south of the interior face of the north exterior wall of the Service Building. The pipe runs west at elevation 581.5 into the Service Building between column lines S6 and S7 and terminates at a LR boundary valve approximately 2 feet east of column line S6. There is a small bore branch line from the main fire
E3 - 10 protection line that is routed vertically through the 586.0 floor slab of the Service Building into a room above and terminates at a license renewal (LR) boundary valve.
In order to maintain the structural integrity of the Service Building to provide its intended functions for the in-scope components, the building area considered in-scope for the structure will be extended two column line bays in the west direction to column line S4 and will include the entire structure in the north-south direction between the personnel corridors on elevations 565.0 and 580.0 and roof at elevation 595.0 south of column line Sa to the north exterior wall of the Service Building. It should be noted that column line S7 is the east exterior wall of the Service Building and is located adjacent and parallel to the west exterior wall of the unit 1 Turbine Building. Additionally, from the foundation slab at El 565.0 (top of floor slab EL 565.0) to the general roof deck of the structure at EL 595.0 and to EL 605.0 above the mechanical equipment room located between column lines S5 and S6 (west to east) and the Pull-Out Space
& Shop Storage between column lines S6 and S7 (west to east) and between column lines Sb to approximately 6 ft north of column line Sh (south to north) defines the in-scope height of the structure.
The pipe supports for the CO2 fire protection system routed between column lines S6 and S7 in the west to east direction and between column lines Wa of the Radwaste Building and Sa of the Service Building and then from Sa and Sf of the Service Building in the south to north direction are in-scope for LR. These supports are scoped and screened in LRA section 2.4.8 and are included with commodity group Non-ASME Equivalent Supports and Components. The AMR evaluation is in LRA section 3.5.1.26.
The pipe supports for the water filled fire protection line that enters the Service Building from the unit 1 Turbine Building at approximately 4.5 south of the interior face of the north exterior wall of the Service Building, routed west at elevation 581.5 into the Service Building between column lines S6 and S7 and terminating at a LR boundary valve approximately 2 feet east of column line S6 are in-scope for LR. The pipe supports for the small bore branch line from the main fire protection line that is routed vertically through the 586.0 floor slab of the Service Building into a room above and terminates at a LR boundary valve are also in-scope for LR. The pipe supports for the fire protection water filled piping are scoped and screened in LRA section 2.4.8 and are included with commodity group Non-ASME Equivalent Supports and Components. The AMR evaluation is in LRA section 3.5.1.26.
UFSAR References Additional details for the Service Building structure is found in UFSAR 12.2.6.2.
License Renewal Drawings The license renewal drawing for the Service Building is listed below.
0-10E201-01-LR Components Subject to AMR The component types that require aging management review are indicated in Table 2.4.7.9, Service Building.
E3 - 11 The aging management review results for these component types are provided in Table 3.5.2.30, Service Building - Summary of Aging Management Evaluation.
Table 2.4.7.9 Service Building Component Type Intended Functions Masonry Block SS(NSR)
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Roof Membrane SP Structural Steel Beams, Columns, Plates, and Trusses SS(NSR)
E3 - 12 3.5.2.1.29 Service Building Materials The materials of construction for Service Building components are:
Carbon and low alloy steel Masonry block Reinforced concrete Roof Membrane (Insulation, flashing, sealants and wood nailers)
Environment Service Building components are exposed to the following environments:
Buried Inside air Outside air Aging Effects Requiring Management The following aging effects associated with the Service Building require management:
Cracking, loss of bond, loss of material (spalling, scaling) due to corrosion of embedded steel Cracks, distortion, increase in component stress level due to settlement Expansion and cracking due to reaction with aggregates Increase in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack Increase in porosity and permeability, loss of strength due to leaching of calcium hydroxide Loss of material (spalling, scaling) and cracking due to freeze-thaw Loss of material due to general corrosion Loss of weatherproofing integrity due to shrinkage, cracking, drying, separation, organic decomposition, wear, weathering Aging Management Programs The following aging management programs manage the aging effects for Service Building components.
Masonry Wall Program (B.2.1.35)
Structures Monitoring Program (B.2.1.36)
E3 - 13 Table 3.5.2.30: Service Building - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG -
1801 Vol. 2 Item Table 1 Item Notes Masonry Block SS(NSR)
Masonry Inside Air Cracks due to restraint, shrinkage, creep, aggressive environment Masonry Wall Program (B.2.1.35)
III.A3.3-a 3.5.1.24 A
Carbon and Low Alloy Steel Inside Air Loss of material due to general corrosion.
Structures Monitoring Program (B.2.1.36)
III.A3.2-a 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried Loss of material (spalling, scaling) and cracking due to freeze-thaw.
Structures Monitoring Program (B.2.1.36)
III.A3.1-a 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-b None I, 2 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-c None I, 3 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-e None I, 4 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried None None III.A3.1-g None I, 5 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Buried Cracks, distortion, increase in component stress level due to settlement.
Structures Monitoring Program (B.2.1.36)
III.A3.1-h 3.5.1.25 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air Expansion and cracking due to reaction with aggregates.
Structures Monitoring Program (B.2.1.36)
III.A3.1-c 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air Cracking, loss of bond, loss of material (spalling, scaling) due to corrosion of embedded steel.
Structures Monitoring Program (B.2.1.36)
III.A3.1-d 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air Increase in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack.
Structures Monitoring Program (B.2.1.36)
III.A3.1-f 3.5.1.20 A
E3 - 14 Table 3.5.2.30: Service Building - Summary of Aging Management Evaluation Component Type Intended Function Material Environment Aging Effect Requiring Management Aging Management Program NUREG -
1801 Vol. 2 Item Table 1 Item Notes Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air Cracks, distortion, increase in component stress level due to settlement.
Structures Monitoring Program (B.2.1.36)
III.A3.1-h 3.5.1.25 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Inside Air None None III.A3.1-j None I, 1 Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Loss of material (spalling, scaling) and cracking due to freeze-thaw.
Structures Monitoring Program (B.2.1.36)
III.A3.1-a 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Increase in porosity and permeability, loss of strength due to leaching of calcium hydroxide.
Structures Monitoring Program (B.2.1.36)
III.A3.1-b 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Expansion and cracking due to reaction with aggregates.
Structures Monitoring Program (B.2.1.36)
III.A3.1-c 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Cracking, loss of bond, loss of material (spalling, scaling) due to corrosion of embedded steel.
Structures Monitoring Program (B.2.1.36)
III.A3.1-d 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Increase in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack.
Structures Monitoring Program (B.2.1.36)
III.A3.1-f 3.5.1.20 A
Reinforced Concrete Beams, Columns, Walls, and Slabs SP, SS(NSR)
Reinforced Concrete Outside Air Cracks, distortion, increase in component stress level due to settlement.
Structures Monitoring Program (B.2.1.36)
III.A3.1-h 3.5.1.25 A
Roof Membrane SP Roof Membrane Outside Air Loss of weatherproofing integrity due to cracking, drying, organic decomposition, separation, shrinkage, wear, weathering.
Structures Monitoring Program (B.2.1.36)
None None J, 6 Structural Steel Beams, Columns, Plates, Trusses SS(NSR)
Carbon and Low Alloy Steel Inside Air Loss of material due to general corrosion.
Structures Monitoring Program (B.2.1.36)
III.A3.2-a 3.5.1.20 A
E3 - 15 Table Notes:
Industry Standard Notes:
Note A Consistent with NUREG-1801 item for component, material, environment, and aging effect. The AMP is consistent with NUREG-1801.
Note I Aging effect in NUREG-1801 item for this component, material and environment combination is not applicable.
Note J Neither the component nor the material and environment combination is evaluated in NUREG-1801.
Plant Specific Notes:
1 Conditional requirements for elevated temperature are satisfied. Therefore, a plant specific aging management program is not required. See further evaluation in Section 3.5.2.2.2.1.
2 For increase in porosity and permeability, loss of strength due to leaching of calcium hydroxide of concrete in inaccessible areas, no plant specific aging management is required. See further evaluation in Section 3.5.2.2.2.1.
3 For expansion and cracking due to reaction with aggregates of concrete in inaccessible areas, no aging management is required. See further evaluation in Section 3.5.2.2.2.1.
4 For cracking, loss of bond, loss of material (spalling, scaling) due to corrosion of embedded steel in concrete for inaccessible areas, no plant specific aging management is required. See further evaluation in Section 3.5.2.2.2.2.
5 For increase in porosity and permeability, cracking, loss of material (spalling, scaling) due to aggressive chemical attack of concrete for inaccessible areas, no plant specific aging management is required. See further evaluation in Section 3.5.2.2.2.2.
6 The aging effects and AMP identified for this material/environment combination are consistent with industry guidance.