NL-16-1245, Edwin I. Hatch, Units 1 and 2, Updated Final Safety Analysis Report, Reference Drawings. Part 10 of 22

Edwin I. Hatch, Units 1 and 2, Updated Final Safety Analysis Report, Reference Drawings. Part 10 of 22

ML16244A463
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Site:	Hatch
Issue date:	08/25/2016
From:	Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
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Document Insertion Sheet.dot Revised by SNC per Document No.: A-47039 ABN H02887 Version 1.0 Document Ver.: 2.0 By: PVK Checked: LCF Approved: RKF Date: 05/02/2013 D O C U M E N T I N S E R T I O N S H E E T E. I. Hatch Nuclear Plant - Unit No. 1 / 2 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

Description Remove Insert 1. This insertion sheet Existing Sheet(s)

Front of Manual

2. Replace Review Summary Sheet 1 of 362 to correct error identified Per SNC460325

, (pdf page 2 of 364)

Existing Sheet(s)

SNC Ver. 2.0

3. Replace Review Summar y Sheet 171 of 363 to correct error identified Per SNC460325, (pdf page 172 of 364)

Existing Sheet(s)

SNC Ver. 2.0

Southern Company Services, In

c. for Georgia Power Company "This document contains proprietary, confidential, and/or trade secret information of the subsidiaries of the Southern Company or of third parties. It is intended for use only by employees of, or authorized contractors of, the subsidiaries of the Southern Company. Unauthorized possession, use, distribution, copying, dissemination, or disclosure of any portion hereof is prohibited."EDWIN I. HATCH NUCLEAR PLANT UNITS 1 & 2 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

Word 2007 PROJECT I.D

.DRAWING NUMBER SHEET VER. Drawn: Designed: Date:06/14/2012 A-47039 1 of 362 2.0 LICENSE RENEWAL AGING MANA GEMENT REVIEW

SUMMARY

Note:

This Aging Management Review Summary provides for compliance with 10 CFR 54.37(b) for E.I. Hatch Nuclear Plant (HNP) regarding inclusion of systems, structures, and components (SSCs) newly identified subsequent to issuance of t he renewed operating license in the FSAR, as appropriate. This Aging Management Review Summary is incorporated by reference into the HNP FSAR.

The two key aspects of this document are: 1. LRA System description information regar ding the intended functions performed by the system. 2. Aging management review (AMR) results for each LRA System within the scope of license renewal. See NMP-ES-063 and sub-tier instructions fo r information on how to use this document.

TABLE OF CONTENTS 1 GENERAL INFORMATION 1.1 Introduction 3 1.2 Definitions 3 1.3 Content and Use 4 1.4 Development Methodology 8 2 TECHNICAL INFORMATION 2.0 Systems and Structures Within the Scope of License Renewal 9 2.1 Reactor, Nuclear Boiler, and Reactor Recirculation Systems 14 2.2 Engineered Safety Features 32 2.3 Auxiliary Systems 78 2.4 Steam and Power Conversion Systems 166 2.5 Structures and Component Supports 174 2.6 Electrical Components 219 3 REFERENCES 3.1 Edwin I. Hatch License Renewal Docket 238 3.2 NRC References 238 3.3 Other References 238 APPENDIX A - 10 Program Elements 240 APPENDIX B - Typical Structure, Component and Commodity Groupings

and Active/Passive Determinations for the Integrated Plant Assessment 245 APPENDIX C - Hatch LR Emails from Ray Baker (SNC) to William Burton (NRC) 261 Page 1-1 1 GENERAL INFORMATION 1.1 Introduction This Aging Management Review Summary provides for compliance with 10 CFR 54.37(b) for E.I. Hatch Nuclear Plant (HNP) regarding inclusion of systems, structures, and components (SSCs) newly identified subsequent to issuance of the renewed operating license in the FSAR, as appropriate. This

Aging Management Review Summary is incorporated by reference into the HNP FSAR. The License Renewal Rule, Section 10 CFR 54.37 contains the following record-keeping requirements: §54.37 Additional records and record-keeping requirements. (a) The licensee shall retain in an auditable and retrievable form for the term of the renewed operating license all information and documentation required by, or otherwise necessary to document compliance with, the provisions of this part. (b) After the renewed license is issued, the FSAR update required by 10 CFR 50.71(e) must include any systems, structures, and components newly identified that would have been subject to an aging management review or evaluation of time-limited aging analyses in accordance with §54.21.

This FSAR update must describe how the effects of aging will be managed such that the intended function(s) in §54.4(b) will be effectively maintained during the period of extended operation.

1.2 Definitions For use in the SNC process, the following key definitions are provided:

"New LR Scope" SSCs are those SSCs that were not included within the scope of license renewal at the time of the issuance of the renewed operating license, but which now:

I. Perform one or more of the intended functions described in 10 CFR54.4: 1. 10 CFR 54.4(a)(1) Safety Related Components

2. 10 CFR 54.4(a)(2) Non-safety Related Components potentially affecting Safety-Related Components 3. 10 CFR 54.4(a)(3) Relied on to demonstrate compliance with regulations for:

• Fire Protection - 10 CFR 50.48

• Environmental Qualification - 10 CFR 50.49

• Pressurized Thermal Shock - 10 CFR 50.61

• Anticipated Transients without SCRAM - 10 CFR 50.62

• Station Blackout - 10 CFR 50.63 AND which are II. Passive [10 CFR 54.21(1)] and long-lived [10 CFR 54.21(2)]

AND which were III Already installed in the plant when the renewed license was issued on January 15, 2002.

Page 1-2 In effect, "New LR Scope" SSCs are SSCs which would have been subject to aging management review if identified prior to issuance of the renewed operating license.

"Newly Identified" SSCs are those SSCs which meet criteria I, II, and III above, but also are determined (by review against this Aging Management Summary) not to have a previously documented system specific aging management review. That is, for the SSC's system, an aging management review item which addresses the component type, intended function(s), material(s), and environment(s) is not included in this Aging Management Summary. These newly identified SSCs must undergo aging management review, with the results added to this Aging Management Review Summary and the FSAR Supplement. A newly identified determination may result from a CLB change, design change, Condition Report, or operating experience review. Once an SSC is determined to be newly identified through use of SNC procedures and this Aging Management Review Summary, new AMR results information must be added to this Aging Management Review Summary . Other definitions applicable to this Aging Management Review Summary are contained in the SNC License Renewal Implementation Program, NMP-ES-063. 1.3 Content and Use Sections 1.3.1 and 1.3.2 describe the general content of the two key aspects of this Aging Management Review Summary. Use information provided in this Aging Management Review Summary is not intended to specify the processes and procedures by which SNC personnel will enter information into this Aging Management Review Summary or perform 10 CFR 54.37(b) evaluations required to update this Aging Management Review Summary. See References 3.3.1, 3.3.2, 3.3.3, 3.3.5, 3.3.7, 3.3.9, and 3.3.11 for procedural guidance on the use of this Aging Management Review Summary. 1.3.1 System Identification Lists and System Description Information

Content Section 2.0 of this Aging Management Review Summary identifies the systems included within the scope of license renewal (LRA Systems). For NRC review purposes, HNP systems were grouped /

classified into LRA Systems that generally follow the systems outlined in NUREG-1800, Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants. Performance of aging management reviews on these higher level LRA Systems allows for less duplication of aging management reviews (AMRs). Sections 2.1 through 2.6 contain LRA System description information regarding the intended functions performed by the system. This information is pr edominantly extracted from the License Renewal Application and is based on FSAR information. The intent of the systems description information provided is to enable SNC personnel to make a determination as to which LRA System the New LR Scope SSC would have been grouped with in the Integrated Plant Assessment (IPA). The LRA System description information is not intended to define the extents of the license renewal boundary. It is a tool for identifying the proper LRA System bin for AMR purposes only. Scoping basis documentation and license renewal boundary drawings are available to identify the extent of the license renewal boundaries for each LRA System

. Only additions of new LRA Systems to the list of systems within the scope of license renewal are required. Deletions of systems specifically excluded from the scope of license renewal are NOT

required.

Page 1-3 Use System listings and descriptions are used to determine if New LR Scope SSC(s) are addressed by an LRA System already within the scope of license renewal, or if inclusion of the SSC(s) will result in identification of a new LRA System within the scope of license renewal. 1.3.2 Aging Management Review Results

Content Sections 2.1 through 2.6 contain aging management review (AMR) results for each LRA System within the scope of license renewal. These AMR results are presented in tabular form following the system description information for each LRA System. AMR results are presented at the same level of detail as originally contained in the LRA, as amended by docketed correspondence, which is the level of detail originally required for NRC staff acceptance. When the LRA system is within the scope of license renewal for both Units 1 and 2, no distinction is made between the Units, and an AMR originally applicable only to one Unit may be applied to the alternate Unit without the need to revise this Aging Management Review Summary. AMRs have been performed for HNP:

• As part of the original license renewal process, with the results presented in the E.I. Hatch License Renewal Application,

• As part of the NRC review process, with results presented in SNC responses to NRC requests for additional information, And,

• Subsequent to issuance of the renewed operating license in accordance with SNC procedures and processes contained in References 3.3.1, 3.3.2, 3.3.3, 3.3.5, 3.3.7, 3.3.9, and 3.3.11. The "Aging Management Review Results" Tables contain the following seven columns:

• Column 1 - Component Type This column identifies the component types r equiring aging management review for the system or structure. Component types are generally based on the list of component types provided in Appendix B of NEI 95-10.

Component types are in many cases "groupings" of system components (e.g. piping and fittings). For some key system components (e.g. pumps, heat exchangers, vessels), the component or assembly may be specifically identified.

• Column 2 - Intended Function This column identifies the applicable intended function(s) for each component type.

• Column 3 - Material

This column identifies the material(s) of construction for each component type. Materials of construction are presented at a "material class" level (e.g. stainless steel, carbon steel) based upon similar aging effects requiring management, not at the "material grade" level (e.g. 304L, CF8, A193 B7).

Page 1-4

• Column 4 - Environment This column identifies the environment(s) for each component type. Where applicable, environment subcategories have been utilized to clarify the specific environment for the component type. For example, raw water environment subcategories include river water, potable water, and drainage.

• Column 5 - Aging Effects Requiring Management This column identifies the aging effects requiring management for each component type, material, and environment combination. The aging effects requiring management are those effects that must be managed to maintain the intended function of the component type for the period of extended operation.

• Column 6 - Aging Management Programs This column identifies the aging management programs credited for each component type to demonstrate that the aging effects requiring management will be adequately managed such that the intended function of the component type will be maintained for the period of extended operation. An acceptable aging management program should consist of the 10 elements described in Appendix A of NUREG-1800, Revision 2.

Reference 3.3.13 contains the set of site specific aging management programs credited for license renewal.

• Column 7 - Comments

This column is used to identify AMR line items that were added or altered during the NRC review process, but prior to issuance of the renewed operating license. Subsequent to issuance of the renewed operating license, this column is used to identify "newly identified" SSC AMR items and provides reference to the engineering, licensing, or material replacement process which resulted in a "newly identified" conclusion. This column may also be used to provide clarifying or amplifying information to aid in understanding the aging management review issues encompassed by the line item.

Component functions, materials, environments, aging effects, and aging management programs are specifically defined for each site and used in the LRA. Reference 3.3.9 contains the site specific lists for these parameters, except for aging management programs that are listed in Reference 3.3.13. AMR line items included within this Aging Management Review Summary are historical. As such, this Aging Management Review Summary will be updated only when new AMR line items are required. Removal of line items when SSCs are removed from the scope of license renewal is not required.

Use: For all "New LR Scope" SSCs that are addressed by an LRA System within the scope of license renewal, the SSC is compared against the AMR Results tables contained in Sections 2.1 through 2.6 to determine if an applicable AMR line item already exists. An applicable AMR line item exists if the component type and material/environment combination(s) are shown in the appropriate LRA System AMR Results Table. If an applicable AMR line item exists, then the SSC is NOT "newly identified." If a Page 1-5 new AMR line item must be added to the AMR Results table to address the SSC component type/material/environment combination, then the SCC is "newly identified." Caution: When using the Plant Hatch AMR Results Tables, the user should understand that component type/material/environment combinations having no aging effects are only listed when there were no aging effects for the other environments associated with the component type. For example, stainless steel piping exposed to reactor water and the inside environment will only display the reactor water environment and associated aging effects in the AMR Results Tables, since the AMRs prepared as a part of the original IPA process concluded no aging effects for stainless steels in the inside environment. The user should consider this structure when conducting comparisons of New LR Scope SSCs against the AMR Tables. When necessary, refer to the AMRs originally prepared as a part of the Plant Hatch process.

Page 1-6 1.4 Development Methodology Data contained in this Aging Management Review Summary includes a list of systems within the scope of license renewal, LRA System descriptions, and an AMR Results Table for each LRA System that is determined to be within the scope of license renewal. The LRA System description information is taken from the LRA, as amended during the NRC review pr ocess. These descriptions are based primarily upon FSAR descriptions, with additional information added as needed to address license renewal scope issues. The AMR Results Tables are adapted from the LRA as amended during the NRC review process. Comment items are provided to identify the licensing correspondence, design change, or material change which required the addition of, or change to, the line item. Effort has been made to incorporate the same level of detail into this Aging Management Review Summary that was originally required for NRC acceptance in the Safety Evaluation Report regarding E.I. Hatch License Renewal.

2.0-1 2 TECHNICAL INFORMATION 2.0 Systems and Structures Within the Scope of License Renewal Technical information is provided in the following sections to identify and describe the LRA Systems included within the scope of license renewal, identify those HNP systems specifically excluded from the scope license renewal, and to identify completed AMRs for each HNP LRA System within the scope of license renewal.

Tables 2.0-1a through 2.0-1f below list the HNP systems and structures which are included within the scope of license renewal and for which AMRs have been performed.

These Tables consist of 2 columns:

• LRA System Column 1 provides the "LRA System" name. SNC chose to identify HNP systems for license renewal at a high level consistent with an FSAR level discussion.

• Desc. & AMR Column 2 provides a reference to the ARM Summary section containing a system description and the AMR Results for each LRA System.

Table 2.0-1a Systems and Structures within the Scope of License Renewal - Reactor, Nuclear Boiler, and Reactor Recirculation Systems LRA System Description & AMR Results Reactor Assembly System [B11] Includes: Reactor Pressure Vessel Reactor Internals 2.1.1 Nuclear Boiler System [B21]

2.1.2 Reactor Recirculation System [B31]

2.1.3

2.0-2 Table 2.0-1b Systems and Structures within the Scope of License Renewal - Engineered Safety Features LRA System Description & AMR Results Standby Liquid Control System [C41]

2.2.1 Residual Heat Removal System [E11]

2.2.2 Core Spray System [E21]

2.2.3 High Pressure Coolant Injection System [E41]

2.2.4 Reactor Core Isolation Cooling System [E51]

2.2.5 Standby Gas Treatment System [T46]

2.2.6 Primary Containment Purge and Inerting Sys. [T48]

2.2.7 Post LOCA Hydrogen Recombining System [T49]

(Unit 2 only) 2.2.8

2.0-3 Table 2.0-1c Systems and Structures within the Scope of License Renewal - Auxiliary Systems LRA System Description & AMR Results Control Rod Drive System [C11]

2.3.1 Refueling Equipment System [F15]

2.3.2 Insulation System [L36]

2.3.3 Access Doors System [L48]

2.3.4 Condensate Transfer and Storage System [P11]

2.3.5 Sampling System [P33]

2.3.6 Plant Service Water System [P41]

2.3.7 Reactor Building Closed Cooling Water System [P42]

2.3.8 Instrument Air System Section [P52]

2.3.9 Primary Containment Chilled Water System [P64]

(Unit 2 only) 2.3.10 Drywell Pneumatics System [P70] 2.3.11 Emergency Diesel Generators System [R43] 2.3.12 Cranes, Hoists and Elevator System [T31] 2.3.13 Tornado Vents System [T38] 2.3.14 Reactor Building HVAC System [T41] 2.3.15 Traveling Water Screens/Trash Racks System [W33] 2.3.16 Outside Structures HVAC System [X41] 2.3.17 Fire Protection System [X43] 2.3.18 Fuel Oil System [Y52] 2.3.19 Control Building HVAC System [Z41] 2.3.20

2.0-4 Table 2.0-1d Systems and Structures within the Scope of License Renewal - Steam and Power Conversion Systems LRA System Description & AMR Results Electro-Hydraulic Control System [N32]

2.4.1 Main Condenser System [N61]

2.4.2 Table 2.0-1e Systems and Structures within the Scope of License Renewal - Structures and Component Supports LRA System Description & AMR Results Piping Specialties [L35]

2.5.1 Conduits, Raceways, and Trays [R33]

2.5.2 Primary Containment [T23]

2.5.3 Fuel Storage [T24]

2.5.4 Reactor Building [T29]

2.5.5 Drywell Penetrations [T52]

2.5.6 Reactor Building Penetrations [T54]

2.5.7 Turbine Building [U29]

2.5.8 Intake Structure [W35]

2.5.9 Yard Structures [Y29] 2.5.10 Main Stack [Y32] 2.5.11 EDG Building [Y39] 2.5.12 Control Building [Z29] 2.5.13

2.0-5 Table 2.0-1f Systems and Structures within the Scope of License Renewal - Electrical Components LRA System Description & AMR Results Analog Transmitter Trip System [A70]

2.6.1(a) Nuclear Steam Supply Shutoff System [A71]

2.6.1(b) Primary Containment Isolation System [C61]

2.6.1(c) Reactor Protection System [C71]

2.6.1(d) Remote Shutdown System [C82]

2.6.1(e) Process Radiation Monitoring System [D11]

2.6.1(f) Heat Trace System [G13]

2.6.1(g) Plant AC Electrical System [R20] 2.6.1(h) DC Electrical System [R42]

2.6.1(i) Plant Communications System [R51]

2.6.1(j) Power Transformers System [S11]

2.6.1(k) Emergency Response Facilities System [X75]

2.6.1(l) Electrical Panels, Racks, & Cabinets [H11]

2.6.2 Instruments Racks, Panels, & Enclosures [H21]

2.6.3 2.1-1 2.1 REACTOR, NUCLEAR BOILER, AND REACTOR RECIRCULATION SYSTEMS The Reactor Assembly System, Nuclear Boiler System, and Reactor Recirculation Systems are addressed in the following Aging Management Summary sections:

• Reactor Assembly System, Section 2.1.1

• Nuclear Boiler System, Section 2.1.2

• Reactor Recirculation System, Section 2.1.3 2.1.1 Reactor Assembly System [B11]

System Description The reactor vessel has three major purposes:

• Contain core, internals and moderator.

• Serve as a high integrity barrier against leakage.

• Provide a floodable volume.

The reactor assembly consists of the reactor pressure vessel (RPV) and its internal components of the core, shroud, steam separator and dryer assemblies, and jet pumps.

Also included in the reactor assembly are the control rods, control rod drive (CRD) housings, and the CRD. The RPV is a vertical, cylindrical pressure vessel with hemispherical heads of welded construction. The major reactor internal components are the core (fuel, channels, control blades, and instrumentation), the core support structure (including the core shroud, shroud head, separators, top guide, and core support), the steam dryer assembly, and the jet pumps. The reactor internal structural elements are stainless steel or other corrosion-resistant alloys.

The reactor vessel is located inside the primary containment building. The internal environment of the RPV is reactor water, normally at 533 °F and 1055 psia during plant operation. Water quality is maintained within the specified limits. During plant conditions that require the operation of the shutdown cooling mode of RHR, reactor water can be cooled to approximately 117 °F via the RHR heat exchangers and recirculated back to the reactor through the residual recirculating system (RRS) piping.

During plant shutdown conditions, the water temperature in the RPV can be as low as

70°F.

2.1-1 Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Program Comments Appurtenances Pressure Boundary Fission Product Barrier Structural Support Reactor WaterNickel Based Alloy Stainless SteelCracking Boiling Water Reactor Vessel and Internals Program Reactor Water Chemistry Control Component Cyclic or Transient Limit Program Deleted Reactor Pressure Vessel Monitoring Program.

Inspections are contained as a part of the Boiling Water Reactor Vessel and Internals Program as described in Chapter 18 of the FSAR. No changes to program criteria

result. Attachments and Connecting Welds Pressure Boundary Fission Product Barrier Structural Support Reactor WaterCarbon Steel

Low Alloy

Steel Nickel Based

Alloy Stainless SteelCracking Boiling Water Reactor Vessel and Internals Program

Reactor Water Chemistry Control Component Cyclic or Transient Limit Program Deleted Reactor Pressure Vessel Monitoring Program. Inspections are contained as a part of the Boiling Water Reactor Vessel and Internals Program as described in Chapter 18 of the FSAR. No changes to program criteria result. Closure Studs Pressure Boundary Fission Product Barrier Reactor WaterLow Alloy Steel Cracking Boiling Water Reactor Vessel and Internals Program

Component Cyclic or Transient Limit Program Deleted Reactor Pressure Vessel Monitoring Program. Inspections are contained as a part of the Boiling Water Reactor Vessel and Internals Program as described in Chapter 18 of the FSAR. No changes to program criteria result. Control Rod Drive Pressure Boundary Structural Support Reactor WaterStainless SteelCracking Inservice Inspection Program

Reactor Water Chemistry Control Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results 2.1-2 Core Spray Internal Piping Pressure Boundary Reactor WaterStainless SteelCracking Boiling Water Reactor Vessel and Internals Program Inservice Inspection Program

Reactor Water Chemistry Control Core Spray Sparger Pressure Boundary Flow Distribution Reactor WaterStainless SteelCracking Boiling Water Reactor Vessel and Internals Program Inservice Inspection Program

Reactor Water Chemistry Control CRD Housing

and CR Guide Tubes Structural Support Reactor WaterStainless SteelCracking Boiling Water Reactor Vessel and Internals Program Inservice Inspection Program

Reactor Water Chemistry Control Dry Tube Weld to Guide Tube Pressure Boundary Reactor WaterStainless SteelCracking Inservice Inspection Program Reactor Water Chemistry Control Jet Pump Assemblies Pressure Boundary Structural Support Reactor WaterStainless Steel

Cast Austenitic Stainless SteelCracking Boiling Water Reactor Vessel and Internals Program

Inservice Inspection Program Reactor Water Chemistry Control Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results 2.1-3 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Program Comments Nozzles Pressure Boundary Fission Product Barrier Structural Support Reactor WaterLow Alloy Steel Cracking Boiling Water Reactor Vessel and Internals Program

Reactor Water Chemistry Control Component Cyclic or Transient Limit Program Replaced the Reactor Pressure Vessel Monitoring Program with the Boiling Water Reactor Vessel and Internals Program as described in Chapter 18 of the FSAR. No changes to program criteria result. Penetrations Pressure Boundary Fission Product Barrier Structural Support Reactor WaterNickel Based Alloy Stainless SteelCracking Boiling Water Reactor Vessel and Internals Program Reactor Water Chemistry Control Replaced the Reactor Pressure Vessel Monitoring Program with the Boiling Water Reactor Vessel and Internals Program as described in Chapter 18 of the FSAR. No changes to program criteria result. Safe Ends Pressure Boundary Fission Product Barrier Structural Support Reactor WaterStainless Steel Low Alloy Steel Carbon Steel Nickel Based Alloy Cracking Boiling Water Reactor Vessel and Internals Program Reactor Water Chemistry Control Component Cyclic or Transient Limit Program Replaced the Reactor Pressure Vessel Monitoring Program with the Boiling Water Reactor Vessel and Internals Program as described in Chapter 18 of the FSAR. No changes to program criteria result.

Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results 2.1-4 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Program Comments Shell and Closure Heads Pressure Boundary Fission Product Barrier Structural Support Reactor WaterLow Alloy Steel Loss of Fracture Toughness Reactor Pressure Vessel

Material Surveillance Program

Component Cyclic or Transient Limit Program Replaced the Reactor Pressure Vessel Monitoring Program with the Reactor Pressure Vessel Material Surveillance Program as described in Chapter 18 of the FSAR. No changes to program criteria result. Shroud Pressure Boundary

Structural Support Reactor WaterStainless SteelCracking Boiling Water Reactor Vessel and Internals Program

Inservice Inspection Program Reactor Water Chemistry Control Shroud Supports Pressure Boundary Structural Support Reactor WaterStainless Steel Nickel Based

Alloy Low Alloy

Steel Cracking Boiling Water Reactor Vessel and Internals Program

Inservice Inspection Program Reactor Water Chemistry Control Steam Dryer Assembly Physical Integrity Reactor WaterStainless SteelCracking Boiling Water Reactor Vessel and Internals Program This item is conservatively added in response to OE following receipt of the renewed operating license. See letter NL-05-1298.

Table 2.1-1 Reactor Assembly System [B11] - Aging Management Review Results 2.1-5 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Program Comments Thermal Sleeves Pressure Boundary Fission Product Barrier Reactor WaterStainless Steel

Nickel Based Alloy Cracking Boiling Water Reactor Vessel and Internals Program Reactor Water Chemistry Control Component Cyclic or Transient Limit Program Replaced the Reactor Pressure Vessel Monitoring Program with the Boiling Water Reactor Vessel and Internals Program as described in Chapter 18 of the FSAR. No changes to program criteria result. Top Guide Structural Support Reactor WaterStainless SteelCracking Boiling Water Reactor Vessel and Internals Program Inservice Inspection Program

Reactor Water Chemistry Control 2.1-6 2.1.2 Nuclear Boiler System [B21]

System Description The nuclear boiler system is composed of several components and subsystems that are required to generate steam. Functions provided by the nuclear boiler system include supplying feedwater to the reactor, conducting steam from the reactor, reactor overpressure protection, and some reactor control and/or engineered safety feature functions. The nuclear boiler system is in operation any time the plant is in operation. Most of the major components in the system are part of the reactor coolant pressure boundary.

The system contains the following major components:

• Main steam lines (MSLs).

• Safety relief valves (SRVs).

• Main steam isolation valves (MSIVs).

• Feedwater lines.

• Feedwater line check valves.

• Instrumentation and controls.

2.1-7 Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting (Class 1) Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Preload Torque Activities

Inservice Inspection Program Bolting (non-Class 1) Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Preload

Loss of Material Torque Activities

Protective Coatings Program Crack Growth

Monitor (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program Component Cyclic or Transient Limit Program

Treated Water Systems Piping Inspections

Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results 2.1-8 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Flow Nozzle (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material

Cracking Reactor Water Chemistry Control Inservice Inspection Program Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Main Steam Flow Restrictor -

Pipe (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material

Cracking Reactor Water Chemistry Control Inservice Inspection Program Galvanic Susceptibility Inspections Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections This line item was added in response to RAI 2.3.2 -NBS- 2, SNC correspondence HL-5979, dated August 29, 2000.

Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results 2.1-9 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Main Steam Flow Restrictor -

Venturi Flow Restriction Reactor WaterCast Austenitic Stainless Steel Loss of Material Cracking Reactor Water Chemistry Control Component Cyclic or Transient Limit Program This line item was added in response to RAI 2.3.2 -NBS- 2, SNC correspondence HL-5979, dated August 29, 2000.

Piping (non-Class 1) Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material Cracking Reactor Water Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Flow Accelerated Corrosion

Program was removed in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Piping (non-Class 1) Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Piping (non-Class 1) Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material

Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections

Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results 2.1-10 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping (non-Class 1) Pressure Boundary Fission Product Barrier Torus Water Stainless SteelLoss of Material

Cracking Suppression Pool Chemistry Control Torus Submerged Components Inspection Program Removed line item for Piping (non-class 1) - Torus Water - Carbon Steel in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Piping (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program

Galvanic Susceptibility Inspections

Component Cyclic or Transient Limit Program Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Piping (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program

Component Cyclic or Transient Limit Program

Treated Water Systems Piping Inspections

Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results 2.1-11 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping (non-Class 1) Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material

Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Inservice Inspection Program was removed in response to email from R.D. Baker to W.F.

Burton, dated April 21, 2000.

Changed Piping to (non-Class 1). June 20, 2000 email from R.D. Baker to W.F. Burton. Restricting Orifice (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Component Cyclic or Transient Limit Program

Inservice Inspection Program

Treated Water Systems Piping Inspections Thermowell (non-Class 1) Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities

Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results 2.1-12 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Thermowell (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material

Cracking Reactor Water Chemistry Control Inservice Inspection Program Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Valve Bodies (non-Class 1) Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material

Cracking Reactor Water Chemistry Control Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Flow Accelerated Corrosion

Program was removed in response to email from R.D.

Baker to W.F. Burton, dated April 21, 2000.

Valve Bodies (non-Class 1) Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Valve Bodies (non-Class 1) Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Inservice Inspection Program Passive Component Inspection Activities

Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results 2.1-13 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program

Galvanic Susceptibility Inspections

Component Cyclic or Transient Limit Program

Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections Valve Bodies (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program

Component Cyclic or Transient Limit Program

Treated Water Systems Piping Inspections

Table 2.1-2 Nuclear Boiler System [B21] - Aging Management Review Results 2.1-14 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies (Class 1) Pressure Boundary Fission Product Barrier Reactor WaterCast Austenitic

Stainless Steel Loss of Material Cracking Loss of Fracture Toughness Reactor Water Chemistry Control Inservice Inspection Program Component Cyclic or Transient Limit Program Valve Bodies (non-Class 1) Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Valve Bodies (non-Class 1) Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections Component

External Surfaces (< 200 °F) Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.1-15 2.1.3 Reactor Recirculation System [B31]

System Description

The reactor recirculation system (RRS) is one of two core reactivity control systems. The RRS system is part of the reactor coolant pressure boundary. Therefore, it also functions to maintain the pressure boundary during normal operation, transients, and accident scenarios to prevent the release of radioactive liquid and gas.

RRS consists of two parallel loops, each consisting of a recirculation pump, suction and discharge block valves, piping, fittings, flow elements and connections supporting flow, and differential pressure instrumentation. The RRS interfaces with the residual heat removal (RHR) and reactor water cleanup (RWCU) systems to provide a flow-path in support of shutdown cooling, low pressure coolant injection (LPCI), RWCU, and reactor water level control functions.

HNP FSAR References More information about this system may be found in Unit 1 FSAR Section 4.3 and Unit 2 FSAR subsection 5.5.1.

2.1-16 Table 2.1-3 Reactor Recirculation System [B31] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting (Class 1)

Fission Product Barrier Pressure Boundary Containment Atmosphere Carbon Steel Loss of Preload Loss of Material Cracking Inservice Inspection Program Torque Activities Flow Nozzle (Class 1)

Fission Product Barrier Pressure Boundary Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program

Component Cyclic or Transient Limit Program Piping (Class 1)

Fission Product Barrier Pressure Boundary Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program

Component Cyclic or Transient Limit Program

Treated Water Systems Piping Inspections Pump Casings and Cover (Class 1)

Fission Product Barrier Pressure Boundary Reactor WaterCast Austenitic

Stainless Steel Loss of Material Cracking Loss of Fracture Toughness Reactor Water Chemistry Control Inservice Inspection Program

Component Cyclic or Transient Limit Program

2.1-17 Table 2.1-3 Reactor Recirculation System [B31] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Thermowell (Class 1)

Fission Product Barrier Pressure Boundary Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program

Component Cyclic or Transient Limit Program Treated Water Systems Piping Inspections Valve Bodies (Class 1)

Fission Product Barrier Pressure Boundary Reactor WaterCast Austenitic

Stainless Steel Loss of Material Cracking Loss of Fracture Toughness Reactor Water Chemistry Control Inservice Inspection Program

Component Cyclic or Transient Limit Program Valve Bodies (Class 1)

Fission Product Barrier Pressure Boundary Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Inservice Inspection Program

Component Cyclic or Transient Limit Program

Treated Water Systems Piping Inspections

2.2-1 2.2 Engineered Safety Features The Reactor Assembly System, Nuclear Boiler System, and Reactor Circulation Systems are addressed in the following sections:

• Standby Liquid Control System, Section 2.2.1

• Residual Heat Removal System, Section 2.2.2

• Core Spray System, Section 2.2.3

• High Pressure Coolant Injection System, Section 2.2.4

• Reactor Core Isolation Cooling System, Section 2.2.5

• Standby Gas Treatment System, Section 2.2.6

• Primary Containment Purge and Inerting System, Section 2.2.7

• Post LOCA Hydrogen Recombining System, Section 2.2.8 2.2.1 Standby Liquid Control System [C41]

System Description The standby liquid control system assures reactor shutdown, from full power operation to cold subcritical, by mixing a neutron absorber with the primary reactor coolant. The system is designed for the condition when an insufficient number of control rods can be inserted from the full power setting. The neutron absorber is injected within the core zone in sufficient quantity to provide a sufficient margin for leakage or imperfect mixing. The system is not a scram or a backup scram system for the reactor; it is an independent backup system for the control rod drive (CRD) system.

HNP FSAR References More information can be found on this system in Unit 2 FSAR subsection 4.2.3.

2.2-2 Table 2.2-1 Standby Liquid Control System [C41] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Stainless SteelLoss of Preload Torque Activities Piping Pressure Boundary Borated WaterStainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections Pump Accumulators Pressure Boundary Borated WaterCarbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Protective Coatings Program Pump Casing Pressure Boundary Borated WaterStainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections Tanks Pressure Boundary Borated WaterStainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Thermowell Pressure Boundary Borated WaterStainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections

Table 2.2-1 Standby Liquid Control System [C41] - Aging Management Review Results 2.2-3 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Borated WaterStainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Component

External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program &

Sect. 3.3.2.1. Insulation Protect and Insulate Components Inside Various Insulating Materials Loss of Material Cracking Change in Material Properties Equipment and Piping Insulation Monitoring Program FSAR 18.3.4, Equipment and Piping Insulation Program HL-6002, Sect. VI. B.2.4, Equipment and Piping Insulation Monitoring Program.

NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program

2.2-4 2.2.2 Residual Heat Removal System [E11]

System Description The residual heat removal (RHR) system is composed of several components and subsystems which are required to: Restore and maintain reactor vessel water level after a loss of coolant accident (LOCA); Limit temperature and pressure inside the containment after a LOCA; Remove heat from the suppression pool water; and Remove decay and residual heat from the reactor core to achieve and maintain a cold shutdown condition ; and Remove airborne particulates from the containment atmosphere after a LOCA.

Note that the RHR service water functions are included in E11.

The RHR system consists of four pumps and two heat exchangers divided into two loops of two pumps and one heat exchanger each, plus the associated instruments, valves, and piping. The RHR pumps take suction from the suppression pool or the reactor coolant recirculation loop. The pumps discharge into the recirculation loop, the suppression pool, the containment spray headers, the spent-fuel pool cooling and cleanup system, depending upon the desired mode of system operation. The RHR system interfaces with the recirculation system to provide a flow-path in support of shutdown cooling and low pressure coolant injection (LPCI). The RHR system is part of the reactor coolant pressure boundary; therefore, it also maintains the pressure boundary during normal operation, transients, and accident scenarios to prevent the release of radioactive liquid and gas.

The RHR system is cooled through the heat exchangers by the residual heat removal service water (RHRSW) system. The RHRSW takes suction from the Altamaha River. There are four RHRSW pumps per unit. The RHRSW system also serves as a standby coolant supply system by providing a means of injecting makeup water from the river to the RHR system to keep the core covered during an extreme emergency.

HNP FSAR References More information about the RHR system may be found in Unit 1 FSAR Section 4.8 and Unit 2

FSAR subsection 5.5.7.

2.2-5 Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Bolting Pressure Boundary Inside Stainless SteelLoss of Preload Torque Activities Conductivity

Element Pressure Boundary Fission Product Barrier Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Heat Exchanger Channel Assembly Pressure Boundary Raw Water Carbon Steel Loss of Material Cracking Fouling Loss of Heat Exchanger Performance RHR Heat Exchanger Augmented Inspection and Testing Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program

Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results 2.2-6 Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Heat Exchanger Impingement Plate Shelter/

Protection Torus Water Stainless SteelLoss of Material Cracking Fouling Loss of Heat Exchanger Performance RHR Heat Exchanger Augmented Inspection and Testing Program

Suppression Pool Chemistry Control Heat Exchanger Shell Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Fouling Loss of Heat Exchanger Performance RHR Heat Exchanger Augmented Inspection and Testing Program

Inservice Inspection Program Suppression Pool Chemistry Control Heat Exchanger Tube Sheet Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Fouling Loss of Heat Exchanger Performance RHR Heat Exchanger Augmented Inspection and Testing Program

Suppression Pool Chemistry Control Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results 2.2-7 Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Heat Exchanger Tube Sheet Pressure Boundary Raw Water Stainless Steel Clad Carbon

Steel Loss of Material Cracking Fouling Loss of Heat Exchanger Performance RHR Heat Exchanger Augmented Inspection and Testing Program

PSW and RHRSW Chemistry Control Program Structural Monitoring Program Heat Exchanger Tubes Pressure Boundary Fission Product Barrier Exchange Heat Torus Water Stainless SteelLoss of Material

Cracking Loss of Heat Exchanger Performance RHR Heat Exchanger Augmented Inspection and Testing Program

Suppression Pool Chemistry Control Heat Exchanger Tubes Pressure Boundary Fission Product Barrier Exchange Heat Raw Water Stainless SteelLoss of Material Cracking Fouling Loss of Heat Exchanger Performance RHR Heat Exchanger Augmented Inspection and Testing Program

PSW and RHRSW Chemistry Control Program Structural Monitoring Program

Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results 2.2-8 Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Piping Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Piping Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material

Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Piping Pressure Boundary Buried Carbon Steel with Coal Tar

Enamel Coating Loss of Material ISI Program (VT-2)

Protective Coatings Program This line item was added in response to Open Item 3.1.13-1 (a), SNC correspondence HL-6092, dated June 5, 2001. Piping Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage

Cracking Loss of Heat Exchanger Performance PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Galvanic Susceptibility Inspections

Structural Monitoring Program

Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results 2.2-9 Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Pump Casings Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material

Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Pump Casings

- Bowl Assembly Pressure Boundary Raw Water Cast Austenitic

Stainless Steel Loss of Material Flow Blockage

Loss of Heat Exchanger Performance PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Structural Monitoring Program Cracking was removed as an AERM in response to email from R.D. Baker to W.F. Burton dated June 20, 2000.

Pump Column Discharge Head Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage

PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Galvanic Susceptibility Inspections Structural Monitoring Program Cracking was removed as an AERM in response to email from R.D. Baker to W.F. Burton dated June 20, 2000.

Pump Sub Base Structural Support Inside Carbon Steel Loss of Material Protective Coatings Program Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results 2.2-10 Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Restricting Orifices Pressure Boundary Fission Product Barrier Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspection Restricting

Orifices Pressure Boundary Fission Product Barrier Flow Restriction Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspection Restricting Orifices Pressure Boundary Flow Restriction Raw Water Stainless SteelLoss of Material Flow Blockage Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Structural Monitoring Program Strainer Bodies Debris Protection Raw Water Carbon Steel Loss of Material Flow Blockage Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Galvanic Susceptibility Inspections

Structural Monitoring Program

Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results 2.2-11 Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Strainer Basket Debris Protection Raw Water Stainless SteelLoss of Material Flow Blockage

PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Line item added in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000.

Strainers Debris Protection Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Torus Submerged Components Inspection Program Thermowell Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Tubing Pressure Boundary Raw Water Copper Alloy Loss of Material

Flow Blockage Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Structural Monitoring Program

Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results 2.2-12 Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Valve Bodies Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspection Treated Water Systems Piping Inspection Valve Bodies Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Galvanic Susceptibility Inspections Structural Monitoring Program Component

External Surfaces (< 200 °F) Pressure Boundary Fission Product Barrier Inside Outside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program &

Sect. 3.3.2.1.

Table 2.2-2 Residual Heat Removal System [E11] - Aging Management Review Results 2.2-13 Mechanical Component Component Functions EnvironmentMaterial Aging EffectsAging Management Program/Activity Comments Insulation Protect and Insulate Components Inside Various Insulating Materials Loss of Material Cracking Change in Material Properties Equipment and Piping Insulation Monitoring Program FSAR 18.3.4, Equipment and Piping Insulation Program HL-6002, Sect. VI. B.2.4, Equipment and Piping Insulation Monitoring Program.

NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program

2.2-14 2.2.3 Core Spray System [E21]

System Description The core spray (CS) system is one of the emergency core cooling systems (ECCSs) which protects the core from overheating in the event of a loss of coolant accident (LOCA). The CS system is a low pressure system. Actuation of the CS system results from low reactor vessel water level (level 1) or high drywell pressure or manual action.

Injection valves to the reactor require a signal from the reactor low pressure permissive switches before opening to provide over-pressure protection to the system. The pumps take suction from the suppression pool and spray on the top of fuel assemblies to cool the core and limit the fuel cladding temperature. An alternate suction source for the CS system, the condensate storage tank (CST), is used primarily for providing reactor pressure vessel (RPV) makeup and an injection test supply during outages, and would not normally be used post accident. The CS system works in conjunction with low pressure coolant injection (LPCI).

The CS system has two independent loops. Each loop includes a 100% capacity centrifugal pump driven by an electric motor, a sparger ring in the reactor vessel above the core, piping, valves, and associated controls and instrumentation.

HNP FSAR References The Core Spray System is described in Unit 1 FSAR subsection 6.4.3 and Unit 2 FSAR paragraph 6.3.2.2.3.

2.2-15 Table 2.2-3 Core Spray System [E21] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Bolting Pressure Boundary Inside Stainless SteelLoss of Preload Torque Activities Piping Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Pump Casings Pressure Boundary

Fission Product Barrier Torus Water Carbon Steel Loss of Material

Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspection Restricting Orifice Pressure Boundary Fission Product Barrier Flow Restriction Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspection

Table 2.2-3 Core Spray System [E21] - Aging Management Review Results 2.2-16 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Strainers Debris Protection Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Torus Submerged Components Inspection Program Valve Bodies Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspection Component

External Surfaces (< 200 °F) Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program &

Sect. 3.3.2.1. Insulation Protect and Insulate Piping Inside Various Insulating Materials Loss of Material Cracking Change in

Material Properties Equipment and Piping Insulation Monitoring Program FSAR 18.3.4, Equipment and Piping Insulation Program

HL-6002, Sect. VI. B.2.4, Equipment and Piping Insulation Monitoring Program.

NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.2-17 2.2.4 High Pressure Coolant Injection System [E41]

System Description

The high pressure coolant injection (HPCI) system supplies makeup coolant into the reactor vessel from a fully pressurized to a preset depressurized condition. Demineralized makeup water is supplied from the condensate storage tank (CST) or treated water from the suppression pool. The flow rate of the system will maintain the reactor vessel coolant inventory until the reactor pressure drops sufficiently to permit the low pressure core cooling systems to automatically inject coolant into the vessel.

The HPCI system consists of a turbine driven pump train, piping, valves, and controls that provide a complete and independent emergency core cooling system (ECCS). A test line permits functional testing of the system during normal plant operation. A minimum flow bypass line bypasses pump discharge flow to the suppression pool to protect the pump in the event of a stoppage in the main discharge line. Reactor vessel steam is supplied to the turbine. Turbine exhaust steam is dumped to the suppression pool.

HNP FSAR References

The HPCI system is further described in the Unit 1 FSAR subsection 6.4.1 and Unit 2 FSAR paragraph 6.3.2.2.1.

.

2.2-18 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Bolting Pressure Boundary

Fission Product Barrier Inside Stainless SteelLoss of Preload Torque Activities Flexible Connector Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Environment changed to Wetted Gas in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000. Piping Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material

Cracking Reactor Water Chemistry Control Galvanic Susceptibility Inspections

Flow Accelerated Corrosion Program Treated Water Systems Piping Inspection Treated Water System Piping Inspection added in response to RAI 3.3-HPCI-1, SNC correspondence HL-6002 dated October 10, 2000; and in response to email from R.D.

Baker to W.F. Burton, dated April 21, 2000.

Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results 2.2-19 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material

Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections

Galvanic Susceptibility Inspections Galvanic Susceptibility Inspections added in response to RAI 3.3-HPCI-2, SNC correspondence HL-6002 dated October 10, 2000. Piping Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Program Treated Water Systems Piping Inspections Piping Pressure Boundary

Fission Product Barrier Torus Water Carbon Steel Loss of Material

Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections

Torus Submerged Components Inspection Program Protective Coatings Program Torus Submerged Components Inspection Program and Protective Coatings Program added in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000 Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results 2.2-20 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Torus Water Stainless SteelLoss of Material

Cracking Suppression Pool Chemistry Control Torus Submerged Components Inspection Program Piping Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Piping Pressure Boundary

Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections Piping Pressure Boundary Fission Product Barrier Buried Stainless SteelNone None Required This line item was added in response to Open Item 3.1.13-1 (a), SNC correspondence HL-6092, dated June 5, 2001.

Piping Pressure Boundary

Fission Product Barrier Reactor WaterStainless SteelLoss of Material

Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Pump Baseplate Structural Support Inside Carbon Steel Loss of Material Protective Coatings Program Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results 2.2-21 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Pump Casings Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material

Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Restricting

Orifice Pressure Boundary Flow Restriction Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Restricting

Orifice Pressure Boundary Flow Restriction Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Program

Treated Water Systems Piping Inspections Cracking added as an AERM in response to RAI 3.3-HPCI-5, SNC correspondence HL-6002 dated October 10, 2000.

Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results 2.2-22 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Restricting Orifice Pressure Boundary Flow Restriction

Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections Suction Strainer Debris Protection Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Torus Submerged Components Inspection Program Thermowell Pressure Boundary Torus Water Stainless SteelLoss of Material

Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Turbine Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Valve Bodies Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections

Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results 2.2-23 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material

Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Treated Water Systems Piping Inspections added in response to RAI 3.3-HPCI-8, SNC correspondence HL-6002 dated October 10, 2000. Valve Bodies Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material

Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities Passive Component Inspection Activities added in response to RAI 3.3-HPCI-9, SNC correspondence HL-6002 dated October 10, 2000.

Table 2.2-4 High Pressure Coolant Injection System [E41] - Aging Management Review Results 2.2-24 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections Valve Bodies Pressure Boundary Fission Product Barrier Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Component External Surfaces (< 200 °F) Pressure Boundary Fission Product Barrier Inside Outside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program &

Sect. 3.3.2.1. Insulation Protect and Insulate Piping Inside Various Insulating Materials Loss of Material Cracking Change in Material Properties Equipment and Piping Insulation Monitoring Program FSAR 18.3.4, Equipment and Piping Insulation Program HL-6002, Sect. VI. B.2.4, Equipment and Piping Insulation Monitoring Program.

NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program 2.2-25 2.2.5 Reactor Core Isolation Cooling System [E51]

System Description The reactor core isolation cooling (RCIC) system is a high pressure coolant makeup system which supports reactor shutdown when the feedwater system is unavailable. The RCIC system provides the capability of maintaining the reactor in a hot standby condition for an extended period. Normally, however, the RCIC system is used until the reactor pressure is sufficiently reduced to permit use of the shutdown cooling mode of the residual heat removal (RHR) system.

The RCIC system consists of a turbine driven pump, piping and valves, and the instrumentation necessary to maintain the water level in the reactor vessel above the top of the active fuel should the reactor vessel be isolated from normal feedwater flow.

HNP FSAR References The system is described in the Unit 1 FSAR, Section 4.7 and Unit 2 FSAR subsection 5.5.6.

2.2-26 Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Preload Loss of Material Torque Activities Protective Coatings Program Bolting Pressure Boundary

Fission Product Barrier Inside Stainless SteelLoss of Preload Torque Activities Flexible Connectors Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Piping Pressure Boundary

Fission Product Barrier Reactor WaterCarbon Steel Loss of Material

Cracking Reactor Water Chemistry Control Galvanic Susceptibility Inspections

Flow Accelerated Corrosion Program Treated Water Systems Piping Inspections

Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results 2.2-27 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Piping Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections Piping Pressure Boundary

Fission Product Barrier Torus Water Stainless SteelLoss of Material

Cracking Suppression Pool Chemistry Control Torus Submerged Components Inspection Program Piping Pressure Boundary

Fission Product Barrier Wetted Gas Carbon Steel Loss of Material

Cracking Gas Systems Component Inspections

Passive Component Inspection Activities

Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results 2.2-28 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Piping Pressure Boundary Fission Production Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Piping Pressure Boundary

Fission Production Barrier Torus Water Carbon Steel Loss of Material

Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Piping Pressure Boundary Fission Production Barrier Buried Stainless SteelNone None Required This line item was added in response to Open Item 3.1.13-1 (a), SNC correspondence HL-6092, dated June 5, 2001.

Pump Baseplate Structural Support Air Carbon Steel Loss of Material Protective Coatings Program Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results 2.2-29 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Pump Casing Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Restricting Orifices Pressure Boundary Flow Restriction

Fission Product Barrier Demin Water Stainless SteelLoss of Material Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections Restricting

Orifices Pressure Boundary Flow Restriction Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Steam Trap Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections

Flow Accelerated Corrosion Program Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results 2.2-30 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Steam Trap Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Steam Trap Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Steam Trap Pressure Boundary

Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections Strainer-Steam Exhaust Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities Suction Strainer Debris Protection Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Torus Submerged Components Inspection Program Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results 2.2-31 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Thermowell Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Thermowell Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections Turbine Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Valve Bodies Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections

Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results 2.2-32 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material Cracking Reactor Water Chemistry Control Flow Accelerated Corrosion Program Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material

Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Cracking was added as an AERM in response to RAI 3.3-RCIC-7 and RAI 3.3-HPCI-5, SNC correspondence HL-6002 dated October 10, 2000.

Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results 2.2-33 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Suppression Pool Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Fission Product Barrier Torus Water Cast Austenitic

Stainless Steel Loss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Valve Bodies Pressure Boundary

Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections

Passive Component Inspection Activities was removed in response to email from R.D.

Baker to W.F. Burton, dated April 21, 2000.

Table 2.2-5 Reactor Core Isolation Cooling System [E51] - Aging Management Review Results 2.2-34 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Component External Surfaces (< 200 °F) Pressure Boundary Fission Product Barrier Inside Outside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program &

Sect. 3.3.2.1.

2.2-35 2.2.6 Standby Gas Treatment System [T46]

System Description The standby gas treatment system (SGTS) is an engineered safety feature (ESF) system for ventilation and cleanup of the primary and secondary containment during certain postulated design basis accidents (DBAs), and meets the design, quality assurance, redundancy, energy source, and instrumentation requirements for ESF systems. The SGTS is also used as a normal means of venting the drywell. The major components of the SGTS include redundant filter trains, control valves, backdraft dampers, fans, and control instrumentation. Each of the filtration assemblies and their respective components are designed for 100-percent-capacity operation.

HNP FSAR References

Additional information may be found for this system in Unit 1 FSAR paragraph 5.3.3.3 and Unit 2 FSAR subsection 6.2.3.

2.2-36 Table 2.2-6 Standby Gas Treatment System [T46] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Damper (frame only) Pressure Boundary Fission Product Barrier Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001. Fan Housing Pressure Boundary Fission Product Barrier Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001. Filter Housing Pressure Boundary

Fission Product Barrier Air Galvanized Steel Cracking None Required Piping Pressure Boundary Fission Product Barrier Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Piping Pressure Boundary Fission Product Barrier Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections

Table 2.2-6 Standby Gas Treatment System [T46] - Aging Management Review Results 2.2-37 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Air Copper Loss of Material Cracking Gas Systems Component Inspections Piping Pressure Boundary Fission Product Barrier Air Galvanized Steel Cracking None Required Piping Pressure Boundary Fission Product Barrier Buried Carbon Steel with Coal Tar Enamel Coating Loss of Material Protective Coatings Program This line item was added in response to Open Item 3.1.13-1 (a), SNC correspondence HL-6092, dated June 5, 2001.

Rupture Disc Pressure Boundary Fission Product Barrier Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Thermowell Pressure Boundary Fission Product Barrier Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections

Table 2.2-6 Standby Gas Treatment System [T46] - Aging Management Review Results 2.2-38 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fission Product Barrier Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Valve Bodies Pressure Boundary Fission Product Barrier Air Gray Cast IronLoss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities Valve Bodies Pressure Boundary

Fission Product Barrier Air Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections Valve Bodies Pressure Boundary Fission Product Barrier Air Copper Alloy Loss of Material Cracking Gas Systems Component Inspections

2.2-39 2.2.7 Primary Containment Purge and Inerting System [T48]

System Description The primary containment purge and inerting system primarily provides and maintains an inert atmosphere in the primary containment for combustible gas control and fire protection.

Plant Technical Specifications require that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of reactor operation, the inerting system injects a sufficient amount of gaseous nitrogen into the drywell and torus so that the oxygen concentration falls below 4% by volume.

Major equipment for the purge and inerting system includes a purge air supply fan, liquid nitrogen storage tank, ambient vaporizer, steam vaporizer, vacuum breaker, valves, piping, controls, and instrumentation. The purge and inerting system provides containment vent paths to the standby gas treatment system which provides a vent path to the main stack for containment vent and purge operations.

HNP FSAR References

More information may be found in Unit 1 FSAR paragraph 5.2.3.8 and 9 and Unit 2 FSAR Section 6.2

.

2.2-40 Table 2.2-7 Primary Containment Purge and Inerting System [T48]- Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Bolting Pressure Boundary Inside Stainless SteelLoss of Preload Torque Activities Flex Hose Pressure Boundary Air Stainless SteelCracking Gas Systems Component Inspections Nitrogen Tank Jacket Structural Support Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Piping Pressure Boundary Torus Water Carbon Steel Loss of Material Cracking Suppression Pool Chemistry Control Torus Submerged Components Inspection Program Protective Coatings Program Galvanic Susceptibility Inspections was removed in response to RAI 3.1.29-5, SNC correspondence HL-6002 dated October 10, 2000.

Protective Coatings Program was added in response to RAI

3.3-P&I-1, SNC correspondence HL-6002 dated October 10, 2000; and in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Table 2.2-7 Primary Containment Purge and Inerting System [T48]- Aging Management Review Results 2.2-41 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Piping Pressure Boundary Dried Gas Stainless SteelCracking None Required Piping Pressure Boundary Wetted Gas Carbon Steel Loss of Material

Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Pressure Buildup Coil Pressure Boundary Exchange Heat Dried Gas Stainless SteelCracking None Required Rupture Disc Pressure Boundary Dried Gas Stainless SteelCracking None Required Storage Tank Pressure Boundary Dried Gas Stainless SteelCracking None Required Thermowell Pressure Boundary Inside Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections Valve Bodies Pressure Boundary Torus Water Stainless SteelLoss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections

Table 2.2-7 Primary Containment Purge and Inerting System [T48]- Aging Management Review Results 2.2-42 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Dried Gas Carbon Steel Cracking None Required Valve Bodies Pressure Boundary Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Vaporizer Pressure Boundary Exchange Heat Dried Gas Stainless SteelCracking None Required Component

External Surfaces (< 200 °F) Pressure Boundary Structural Support Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program &

Sect. 3.3.2.1.

2.2-43 2.2.8 Post LOCA Hydrogen Recombiners System [T49] (Unit 2 only)

System Description The post loss of coolant accident (LOCA) hydrogen recombiner system ensures that hydrogen does not accumulate within the primary containment in combustible concentrations following a LOCA. This is ac complished by drawing primary containment atmosphere from the drywell and passing it through the recombiner where the hydrogen reacts with available oxygen to form water vapor. The recombiner discharge is to the suppression pool (torus).

The hydrogen recombiner system is part of the combustible gas control system and consists of two independent 100% capacity identical trains. Each train consists of three packages: the recombiner skid, the control console, and the power panel.

HNP FSAR References More information can be found about this system in Unit 2 FSAR subsection 6.2.5.

2.2-44 Table 2.2-8 Post LOCA Hydrogen Recombiners System [T49] (Unit 2 only) - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Blower Casing Pressure Boundary

Fission Product Barrier Wetted Gas Carbon Steel Loss of Material

Cracking Gas Systems Component Inspections

Passive Component Inspection Activities This line item is added as a result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-6092, dated June 5, 2001. Instrumentation Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

This line item is added as a result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-6092, dated June 5, 2001. Instrumentation Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections

This line item is added as a result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-6092, dated June 5, 2001. Piping Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections This line item is added as a result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-6092, dated June 5, 2001.

Table 2.2-8 Post LOCA Hydrogen Recombiners System [T49] (Unit 2 only) - Aging Management Review Results 2.2-45 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material

Cracking Gas Systems Component Inspections

Passive Component Inspection Activities Reaction Chamber Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections This line item is added as a result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-6092, dated June 5, 2001. Valve Bodies Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Valve Bodies Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Water Separator Pressure Boundary

Fission Product Barrier Wetted Gas Carbon Steel Loss of Material

Cracking Gas Systems Component Inspections

Passive Component Inspection Activities This line item is added as a result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-6092, dated June 5, 2001.

Table 2.2-8 Post LOCA Hydrogen Recombiners System [T49] (Unit 2 only) - Aging Management Review Results 2.2-46 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Water Spray Cooler Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections This line item is added as a result of Open Item 2.3.3.2-1 (a), SNC correspondence HL-6092, dated June 5, 2001. Component

External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program &

Sect. 3.3.2.1.

2.3-1 2.3 Auxiliary Systems The Auxiliary Systems are addressed in the following sections:

• Control Rod Drive System, Section 2.3.1

• Refueling Equipment System, Section 2.3.2

• Insulation System, Section 2.3.3

• Access Doors System, Section 2.3.4

• Condensate Transfer and Storage System, Section 2.3.5

• Sampling System, Section 2.3.6

• Plant Service Water System, Section 2.3.7

• Reactor Building Closed Cooling Water System, Section 2.3.8

• Instrument Air System Section 2.3.9

• Primary Containment Chilled Water System, Section 2.3.10

• Drywell Pneumatics System, Section 2.3.11

• Emergency Diesel Generators System, Section 2.3.12

• Cranes, Hoists and Elevator System, Section 2.3.13

• Tornado Vents System, Section 2.3.14

• Reactor Building HVAC System, Section 2.3.15

• Traveling Water Screens/Trash Racks System, Section 2.3.16

• Outside Structures HVAC System, Section 2.3.17

• Fire Protection System, Section 2.3.18

• Fuel Oil System, Section 2.3.19

• Control Building HVAC System, Section 2.3.20

• Turbine Building HVAC System, Section 2.3.21 2.3.1 Control Rod Drive (CRD) System [C11]

System Description The CRD hydraulic system provides pressurized, demineralized water for the cooling and manipulation of the CRD mechanisms. In addition, the CRD system provides purge water for the reactor water cleanup (RWCU) pump and reactor recirculation pump seals. The alternate rod insertion system is a subsystem of the CRD system. It is a backup means of scramming the reactor by venting the scram air header. It is completely independent of the reactor protection system (RPS) and was installed for the purpose of reducing the probability of an anticipated transient without scram (ATWS) event. Water enters the CRD system from the condensate header downstream of the condensate demineralizers (normal suction) or from the condensate storage tank (CST) (alternate suction).

The condensate header is the preferred suction source because the water contains less oxygen (deaerated) than water from the CST.

HNP FSAR References More information about this system may be found in Unit 2 FSAR subsections 4.1.3 and 4.2.3.

2.3-2 Table 2.3-1 Control Rod Drive (CRD) System [C11] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Accumulator Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material

Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Galvanic Susceptibility Inspections Treated Water Systems Piping Inspections Accumulator Pressure Boundary Fission Product Barrier Dried Gas Carbon Steel Cracking None Required Bolting (Non-Class 1) Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Piping Pressure Boundary

Fission Product Barrier Demin Water Carbon Steel Loss of Material

Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections

Table 2.3-1 Control Rod Drive (CRD) System [C11] - Aging Management Review Results 2.3-3 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Piping Pressure Boundary Fission Product Barrier Dried Gas Stainless SteelCracking None Required Piping Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Rupture Disc Pressure Boundary Fission Product Barrier Dried Gas Stainless SteelCracking None Required

Table 2.3-1 Control Rod Drive (CRD) System [C11] - Aging Management Review Results 2.3-4 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fission Product Barrier Demin Water Carbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary

Fission Product Barrier Dried Gas Copper Alloy Cracking None Required Valve Bodies Pressure Boundary Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities

Table 2.3-1 Control Rod Drive (CRD) System [C11] - Aging Management Review Results 2.3-5 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fission Product Barrier Air Copper Alloy Cracking None Required Component External Surfaces (< 200 °F) Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.3-6 2.3.2 Refueling Equipment System [F15]

System Description The refueling platform equipment assembly is used for handling and transporting reactor core internals and service and handling equipment associated with the refueling operation. The refueling platform equipment assembly consists of the refueling platform, fuel grapple, grapple headlight, and the hardware required to assemble these components into a workable unit.

The refueling platform is a bridge structure that spans the refueling pool and the reactor well and travels on rails which extend the length of the fuel storage pool and the reactor well. A working platform extends the width of the bridge structure, providing working access to the entire width of the pools and reactor well area. The combination of the bridge movement for the length of the pool and the trolley movement for the width of the pool provides complete access to the open pool and reactor well. The movements of the bridge and trolley are displayed so that positions above known locations, such as the location of in-core fuel assemblies, can be repeatedly reproduced from dials on the trolley cab.

The fuel grapple extends downward, below the underside of the refueling platform, into the pool or reactor well. The telescoping grapple is extended or lowered by a fuel hoist. The position of the air-operated grapple is indicated in the control station.

HNP FSAR References More information on refueling may be found in Unit 1 FSAR Section 7.6 and Unit 2 FSAR Section 9.1

.

2.3-7 Table 2.3-2 Refueling Equipment System [F15] - Aging Management Review Results

Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural support Nonsafety Related Structural Support Inside Carbon steel Loss of Material Protective Coatings Program

Overhead Crane and Refueling Platform Inspection

Structural Monitoring Program Structural Monitoring Program was added in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Miscellaneous

Steel Structural support Nonsafety Related Structural Support Inside Carbon steel Loss of Material Protective Coatings Program

Overhead Crane and Refueling Platform Inspection

Structural Monitoring Program Structural Monitoring Program was added in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Rivets Structural Support Inside Aluminum None None Required Structural

Steel Structural support Inside Carbon steel Loss of Material Protective Coatings Program

Overhead Crane and Refueling Platform Inspection

Structural Monitoring Program Structural Monitoring Program was added in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

2.3-8 2.3.3 Insulation System [L36]

System Description The purpose of insulation is to help retain heat in the process piping and equipment, to prevent moisture from condensing on cold surfaces, to protect equipment and personnel from high temperatures, to prevent piping from freezing in cold areas of the plant, and to protect heat tracing from damage. Insulation is required in conjunction with heat tracing. Insulation is also credited in heat load calculations for safety related rooms. Failure of this insulation could allow the heat load of the room to exceed the capability of the HVAC system, thus exceeding the design temperature of the room.

2.3-9 Table 2.3-3 Insulation System [L36] - Summary of Aging Management Review

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Aluminum Jacket Environmental Control Outside Aluminum Loss of Material Cracking Equipment and Piping Insulation Monitoring Program Insulation Environmental Control Outside Asbestos

Calcium Silicate Fiberglass Loss of Material Cracking Change in Material Properties Equipment and Piping Insulation Monitoring Program Insulation Environmental Control Inside Outside Ceramics Mineral Fiber Loss of Material Cracking Change in Material Properties Equipment and Piping Insulation Monitoring Program Insulation

Bolting Environmental Control Outside Galvanized Steel Loss of Material Cracking Equipment and Piping Insulation Monitoring Program Insulation

Bolting Environmental Control Outside Stainless SteelLoss of Material Cracking Equipment and Piping Insulation Monitoring Program

Table 2.3-3 Insulation System [L36] - Summary of Aging Management Review 2.3-10 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Stainless Steel Jacket Environmental Control Inside Stainless SteelLoss of Material Cracking Equipment and Piping Insulation Monitoring Program Change in Material Properties was removed in response to RAI 3.4-IN-1, SNC correspondence HL-6002 dated October 10, 2000.

Wire for Insulation Environmental Control Outside Carbon Steel Loss of Material Cracking Equipment and Piping Insulation Monitoring Program

2.3-11 2.3.4 Access Doors System [L48]

System Description The purpose of the secondary containment access doors is to provide access for personnel and equipment. The secondary containment provides, in conjunction with the primary containment and other engineering safeguards, the capability to limit the release to the environs of radioactive materials so that offsite dose from a postulated design basis accident w ill be below the guideline values of 10 CFR 100.

2.3-12 Table 2.3-4 Access Doors System [L48] - Summary of Aging Management Review

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Missile Barrier

Fission Product Barrier Inside

Outside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

2.3-13 2.3.5 Condensate Transfer and Storage System [P11]

System Description The condensate transfer and storage system prov ides the plant system makeup, receives reject flow, and provides condensate for any continuous service needs and intermittent batch-type services. The total stored design quantity is based on the demand requirements during refueling for filling the dryer separator pool and the reactor well.

A 500,000 gallon condensate storage tank (CST) supplies the various unit requirements. The system includes two condensate transfer pumps and associated piping and valves. The CST provides the preferred supply to the high pressure coolant injection (H PCI) and reactor core isolation cooling (RCIC) systems. All other suctions are located above suction lines for these systems to provide a 100,000 gallon reserve.

HNP FSAR References The condensate transfer and storage system is described in Unit 1 FSAR Section 11.9 and Unit 2 FSAR subsection 9.2.6.

2.3-14 Table 2.3-5 Condensate Transfer and Storage System [P11] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Outside Stainless SteelLoss of Preload Torque Activities Piping Pressure Boundary Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Tanks Pressure Boundary Demin Water Aluminum Loss of Material Demineralized Water and Condensate Storage Tank Chemistry Control Condensate Storage Tank Inspection Tanks Pressure Boundary Demin Water Galvanized Steel Loss of Material Demineralized Water and Condensate Storage Tank Chemistry Control

Condensate Storage Tank Inspection Tanks Pressure Boundary Demin Water Stainless SteelLoss of Material Demineralized Water and Condensate Storage Tank Chemistry Control Condensate Storage Tank Inspection

Table 2.3-5 Condensate Transfer and Storage System [P11] - Aging Management Review Results 2.3-15 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Demin Water Cast Austenitic Stainless Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspection Valve Bodies Pressure Boundary Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspection Insulation Protect and Insulate Piping Outside Various Insulating Materials and Jacketing Loss of Material Cracking Change in

Material Properties Equipment and Piping Insulation Monitoring Program FSAR 18.3.4, Equipment and Piping Insulation Program

HL-6002, Sect. VI. B.2.4, Equipment and Piping Insulation Monitoring Program.

NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program

2.3-16 2.3.6 Sampling System [P33]

System Description The purpose of the primary containment hydrogen and oxygen analyzing system is to provide a

means of monitoring hydrogen and oxygen in the primary containment (drywell and torus).

The primary containment hydrogen and oxygen analyz ing system consists of two separate, redundant systems, each capable of analyzing the hydrogen and oxygen content from the drywell or torus. Each analyzer channel is operated in parallel from separate penetrations in the drywell and torus. The sample is drawn through a sample cooler by the sample system inlet pump, then pumped to the hydrogen and oxygen analyzer cells. The sample is then returned to the primary containment by the sample system outlet pump.

HNP FSAR References Additional information may be found in Unit 2 FSAR paragraph 6.2.4.3.3.2.

2.3-17 Table 2.3-6 Sampling System [P33] - Aging Management Review Results

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Valve Bodies Pressure Boundary

Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections

]\ 2.3-18 2.3.7 Plant Service Water System [P41]

System Description The plant service water (PSW) system removes the heat generated by the operation of various systems (both safety related and nonsafety related). The PSW also provides makeup water to the plant circulating water system by supplying screened Altamaha river water to

system heat exchangers. After traveling through the heat exchangers, the water is routed to the circulating water flume for use as flume makeup. The heat picked up by the water is rejected to the atmosphere via the plant cooling towers or to the river via the circulating water flume overflow. The PSW system water is also available for fire-fighting, radwaste dilution, and emergency spent fuel pool makeup.

The PSW system consists of four main pumps divided into two divisions of two pumps each. Each of the two divisions supplies one redundant train of safety-related equipment. After passing through isolation valves, the two safety-related headers merge into one header supplying nonsafety-related equipment. After servicing the various systems, the service water is discharged to a potential radioactive contaminant release path, and the discharge header is constantly monitored for activity.

HNP FSAR References The PSW system is described in the Unit 1 FSAR Section 10.7 and Unit 2 FSAR subsection

9.2.1.

2.3-19 Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Outside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Cooling Coil Tubing Pressure Boundary Raw Water Copper Alloy Loss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Flexible Connector Pressure Boundary Raw Water Stainless SteelLoss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Structural Monitoring Program Piping Pressure Boundary Buried Carbon Steel with Coal Tar Enamel Coating Loss of Material ISI Program (VT-2)

Protective Coatings Program This line item was added in response to Open Item 3.1.13-1 (a), SNC correspondence HL-6092, dated June 5, 2001.

Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review

2.3-20 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program

Galvanic Susceptibility Inspections Piping Pressure Boundary Raw Water Stainless SteelLoss of Material Flow Blockage Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Pump Bowl Assembly Pressure Boundary Raw Water Cast Austenitic

Stainless Steel Loss of Material Flow Blockage

PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Structural Monitoring Program Cracking was removed as an AERM in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000.

Pump Discharge Column Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage

PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Structural Monitoring Program Cracking was removed as an AERM in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000.

Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review

2.3-21 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Pump Discharge Head Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage

PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Cracking was removed as an AERM in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000.

Pump Sub Base Structural Support Inside Carbon Steel Loss of Material Protective Coatings Program Restricting

Orifices Pressure Boundary Flow Restriction Raw Water Stainless SteelLoss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Sight Glass

Body Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage

Galvanic Corrosion

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Sight Glass

Body Pressure Boundary Raw Water Stainless SteelLoss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Structural Monitoring Program

Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review

2.3-22 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Strainer Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Strainer Pressure Boundary Raw Water Gray Cast IronLoss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Strainer Basket Debris Protection Raw Water Stainless SteelLoss of Material Flow Blockage

PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Cracking was removed as an AERM in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000.

Strainer Basket Debris Protection Raw Water Gray Cast IronLoss of Material Flow Blockage PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Cracking was removed as an AERM in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000.

Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review

2.3-23 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Thermowell Pressure Boundary Raw Water Carbon Steel Loss of Material Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Structural Monitoring Program was added in response to RAI 3.4-PSW-6, SNC correspondence HL-6002 dated October 10, 2000.

Thermowell Pressure Boundary Raw Water Stainless SteelLoss of Material Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program Structural Monitoring Program was added in response to RAI 3.4-PSW-6, SNC correspondence HL-6002 dated October 10, 2000.

Valve Bodies Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program

Galvanic Susceptibility Inspections Valve Bodies Pressure Boundary Raw Water Stainless SteelLoss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program

Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review

2.3-24 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Raw Water Copper Alloy Loss of Material Flow Blockage

Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program PSW and RHRSW Inspection

Program was added in response to RAI 3.4-PSW-2, SNC correspondence HL-6002 dated October 10, 2000; and in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Venturi Pressure Boundary Raw Water Carbon Steel Loss of Material Flow Blockage Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program Structural Monitoring Program

Galvanic Susceptibility Inspections Component

External Surfaces (< 200 °F) Pressure Boundary Structural Support Inside Outside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program Table 2.3-7 Plant Service Water System [P41] - Summary of Aging Management Review

2.3-25 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Insulation Protect and Insulate Piping Outside Various Insulating Materials and Jacketing Loss of Material Cracking Change in Material Properties Equipment and Piping Insulation Monitoring Program FSAR 18.3.4, Equipment and Piping Insulation Program HL-6002, Sect. VI. B.2.4, Equipment and Piping Insulation Monitoring Program.

NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program

2.3-26 2.3.8 Reactor Building Closed Cooling Water System [P42]

System Description The purpose of the reactor building closed cooling water (RBCCW) system is to provide cooling water to certain auxiliary equipment located in the reactor building.

The RBCCW system is a closed-loop cooling system consisting of three one-half capacity pumps, two full-capacity heat exchangers, a surge tank, and a chemical addition system. The cooling water is conveyed by the pumps to the various system coolers and returned to the pumps by way of the RBCCW heat exchanger. The heat rejected by the RBCCW system to the heat exchanger is removed by the plant service water (PSW) system.

HNP FSAR References The RBCCW system is described in the Unit 1 FSAR Section 10.5 and Unit 2 FSAR subsection

9.2.2.

2.3-27 Table 2.3-8 Reactor Building Closed Cooling Water System [P42] - Aging Management Review Results

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Flexible Connectors Pressure Boundary Closed Cooling Water Stainless SteelLoss of Material Cracking Closed Cooling Water Chemistry Control Treated Water Systems Piping Inspections Flow Element Pressure Boundary Closed Cooling Water Stainless SteelLoss of Material Cracking Closed Cooling Water Chemistry Control Treated Water Systems Piping Inspection Heat Exchanger Shells Pressure Boundary Closed Cooling Water Carbon Steel Loss of Material Cracking Closed Cooling Water Chemistry Control

Treated Water Systems Piping Inspection Piping Pressure Boundary Closed Cooling Water Carbon Steel Loss of Material Cracking Closed Cooling Water Chemistry Control

Treated Water Systems Piping Inspection Piping Pressure Boundary Closed Cooling Water Stainless SteelLoss of Material Cracking Closed Cooling Water Chemistry Control Treated Water Systems Piping Inspection

Table 2.3-8 Reactor Building Closed Cooling Water System [P42] - Aging Management Review Results

2.3-28 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Closed Cooling Water Copper Alloy Loss of Material Cracking Closed Cooling Water Chemistry Control Treated Water Systems Piping Inspection Relief Valve Base Pressure Boundary Closed Cooling Water Copper Alloy Loss of Material Cracking Closed Cooling Water Chemistry Control Treated Water Systems Piping Inspection Temperature Probe Pressure Boundary Closed Cooling Water Copper Alloy Loss of Material Cracking Closed Cooling Water Chemistry Control

Treated Water Systems Piping Inspection Thermowell Pressure Boundary Closed Cooling Water Stainless SteelLoss of Material Cracking Closed Cooling Water Chemistry Control

Treated Water Systems Piping Inspection Valve Bodies Pressure Boundary Closed Cooling Water Carbon Steel Loss of Material Cracking Closed Cooling Water Chemistry Control

Treated Water Systems Piping Inspection Valve Bodies Pressure Boundary Closed Cooling Water Stainless SteelLoss of Material Cracking Closed Cooling Water Chemistry Control Treated Water Systems Piping Inspection

Table 2.3-8 Reactor Building Closed Cooling Water System [P42] - Aging Management Review Results

2.3-29 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Component External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.3-30 2.3.9 Instrument Air System [P52]

System Description The purpose of the instrument air system is to provide dried and filtered air to all of the air operated instruments and valves throughout the entire plant (with the exception of equipment inside the drywell).

The instrument air system is divided into the following two subsystems: Noninterruptible system provides instrum ent air for the operation of certain emergency system components. Interruptible system provides instrument air to all other components not supplied by the noninterruptible system.

The drywell pneumatic system supplies the motive gas for components within the drywell. The requirements for the remainder of the compressed air systems are supplied by three oil-free screw-type compressors. Each compressor discharges into an air receiver which in turn

discharges into a common manifold that feeds the instrument and service air systems.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.11 and Unit 2 FSAR subsection

9.3.1.

2.3-31 Table 2.3-9 Instrument Air System [P52] - Aging Management Review Results

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Air Receiver Pressure Boundary Dried Gas Stainless SteelCracking None Required Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Bolting Pressure Boundary Inside Stainless SteelLoss of Preload Torque Activities Hose Pressure Boundary Dried Gas Stainless SteelCracking None Required Piping Pressure Boundary Dried Gas Carbon Steel Cracking None Required Piping Pressure Boundary Dried Gas Stainless SteelCracking None Required Regulator Pressure Pressure Boundary Dried Gas Carbon Steel Cracking None Required Restricting

Orifice Pressure Boundary Dried Gas Stainless SteelCracking None Required This line added for AST licensing amendments 256 (U1) and 200 (U2) Tubing Pressure Boundary Dried Gas Copper Cracking None Required Valve Bodies Pressure Boundary Dried Gas Stainless SteelCracking None Required Valve Bodies Pressure Boundary Dried Gas Carbon Steel Cracking None Required Valve Bodies Pressure Boundary Dried Gas Copper Alloy Cracking None Required

Table 2.3-10 Primary Containment Chilled Water System [P64] (Unit 2 Only) - Aging Management Review Results 2.3-32 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Component External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.3-33 2.3.10 Primary Containment Chilled Water System [P64] (Unit 2 Only)

System Description The primary containment chilled water system is designed to maintain the drywell area below a maximum volumetric average temperature of 150 °F dry bulb during normal operation by providing chilled water to the drywell fan coil units. The primary containment chilled water system consists of two chilled water recirculation pumps, two centrifugal chillers, a chemical addition tank, a chemical feed pump, and an expansion tank. Each chiller consists of a refrigerant compressor, condenser, cooler, accessories, and controls. Each chilled water recirculation pump circulates chilled water through the respective chiller to the fan coil units.

Service water from the reactor building service water system is circulated through the chiller condensers for cooling. Demineralized water provides a source of makeup water for the chilled water system. The expansion tank, chemical addition tank, and associated makeup water supply are shared with the reactor and radwaste building chilled water system.

HNP FSAR References More information may be found in Unit 2 FSAR subsection 9.4.6 2.3-34 Table 2.3-10 Primary Containment Chilled Water System [P64] (Unit 2 Only) - Aging Management Review Results

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities Protective Coatings Program Cap Pressure Boundary Closed Cooling Water Copper Alloy Loss of Material Cracking Closed Cooling Water Chemistry Control Treated Water Systems Piping Inspections Piping Pressure Boundary Closed Cooling Water Carbon Steel Loss of Material Cracking Closed Cooling Water Chemistry Control Treated Water Systems Piping Inspections Thermowell Pressure Boundary Closed Cooling Water Stainless SteelLoss of Material Cracking Closed Cooling Water Chemistry Control

Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Closed Cooling Water Carbon Steel Loss of Material Cracking Closed Cooling Water Chemistry Control

Treated Water Systems Piping Inspections

Table 2.3-10 Primary Containment Chilled Water System [P64] (Unit 2 Only) - Aging Management Review Results 2.3-35 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Component External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.3-36 2.3.11 Drywell Pneumatics System [P70]

System Description The drywell pneumatic system supplies motive gas to the following equipment inside the drywell: reactor recirculation system sample line isolation valve, reactor pressure vessel (RPV) head vent valve, core spray (CS) system injection testable check valves and bypass valves, primary containment chilled water system control valves, residual heat removal (RHR) system low pressure coolant injection (LPC I) check valves and bypass valves, and nuclear boiler system safety relief valves (SRVs), and main steam isolation valves (MSIVs).

A major portion of the drywell pneumatic system is primarily obsolete and not currently used.

The control air is supplied from the nitrogen makeup system or instrument air. The system components still exist in the plant but are isolated by valve alignment or the lines are physically cut and capped.

The drywell pneumatic system receives motive gas from the Unit 1 or Unit 2 nitrogen storage tanks, the instrument air system, or t he emergency nitrogen hookup stations. The system includes an air receiver, particulate filters, flow sensing elements, and various process piping, valves, and regulators.

Normally all system equipment upstream of the receiver tank is isolated, and system pressure is maintained by the nitrogen back-up supply with alternate supply through the instrument air supply system. Under emergency condition specific components in the drywell will be supplied control air from emergency nitrogen bottles.

2.3-37 Table 2.3-11 Drywell Pneumatics System [P70] - Aging Management Review Results

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Bolting Pressure Boundary Inside Stainless SteelLoss of Preload Torque Activities Filter Housings Pressure Boundary Dried Gas Carbon Steel Cracking None Required Filter Housings Pressure Boundary Dried Gas Stainless SteelCracking None Required Flanges Pressure Boundary Dried Gas Carbon Steel Cracking None Required Flexible Hoses Pressure Boundary Dried Gas Stainless SteelCracking None Required Piping Pressure Boundary Dried Gas Carbon Steel Cracking None Required Piping Pressure Boundary Dried Gas Stainless SteelCracking None Required Tubing Pressure Boundary Dried Gas Copper Cracking None Required Valve Bodies Pressure Boundary Dried Gas Carbon Steel Cracking None Required Valve Bodies Pressure Boundary Dried Gas Stainless SteelCracking None Required Valve Bodies Pressure Boundary Dried Gas Copper Alloy Cracking None Required

Table 2.3-11 Drywell Pneumatics System [P70] - Aging Management Review Results 2.3-38 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Component External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program 2.3-39 2.3.12 Emergency Diesel Generator System [R43]

System Description The purpose of the diesel generators is to provide emergency backup power to 4160 VAC emergency buses E, F, and G in the event of a loss of loss of offsite power. The diesel generators are designed to reach rated speed and voltage within 12 seconds after receiving a start signal. This allows operation of emergency equipment powered from these buses to perform their required function to safely shutdown the plant within the required time.

The emergency diesel generator (EDG) provides a highly reliable source of standby, onsite, ac power. There are five diesel generators supplying standby power to 4.16 kV essential buses: 1E, 1F, 1G of Unit 1; and 2E, 2F, and 2G of Unit 2. Diesel generators 2A and 2C supply buses 2E and 2G respectively. Diesel generator 1B is shared between Units 1 and 2 and can supply power to either 1F or 2F. Diesel generator 1B has a selector switch with "Unit 1 control" and "Unit 2 control

" positions, depending on whether it is supplying bus 1F or 2F. Diesel generators 1A and 1C supply buses 1E and 1G, respectively.

The generator field is supplied dc power by a static exciter. The exciter-regulator provides a controlled current to the generator field winding to maintain and control the generator output voltage.

In the automatic mode of voltage control, the generator output voltage is compared to a reference voltage to produce an error signal. Current transformers measure generator load and produce a proportional output. The load signal and voltage error signal are vectorally summed to produce an output which determines the generator field current and, thereby, the generator output voltage.

In the manual mode, the operator controls generator output voltage by adjusting the voltage control lever on the remote control panel. When the voltage balance relay is energized, the output voltage control is transferred from automatic to manual.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 8.4 and Unit 2 FSAR Section 8.3.

2.3-40 Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Expansion Tank Pressure Boundary Demin Water Carbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections

Galvanic Susceptibility Inspections Filter housing Pressure Boundary Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities Flex Hose Pressure Boundary Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections Flexible Connector Pressure Boundary Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-41 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Demin Water Carbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections

Galvanic Susceptibility Inspections Piping Pressure Boundary Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities Piping Pressure Boundary Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Piping Pressure Boundary Air Galvanized Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities Restricting

Orifice Pressure Boundary Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-42 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Tanks Pressure Boundary Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Valve Bodies Pressure Boundary Demin Water Carbon Steel Loss of Material

Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections

Galvanic Susceptibility Inspections Valve Bodies Pressure Boundary Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Valve Bodies Pressure Boundary Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-43 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Wetted Gas Copper Alloy Loss of Material Cracking

Gas Systems Component Inspections Jacket Water Cooling Subsystem The Jacket Water Cooling Subsystem table is added in response to Open Item 2.3.3.2-1 (b), SNC correspondence HL-6092, dated Jun e 5, 2001.Heater Housing Pressure Boundary Demin Water and AntifreezeCarbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Heat Exchanger Shell Pressure Boundary Heat Transfer Demin Water and AntifreezeCarbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Piping/Tubing Pressure Boundary Demin Water and AntifreezeCarbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-44 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping/Tubing Pressure Boundary Demin Water and AntifreezeCopper Loss of Material Cracking Diesel Generator Maintenance Activities Piping/Tubing Pressure Boundary Demin Water and AntifreezeStainless SteelLoss of Material Cracking Diesel Generator Maintenance Activities Pump Casing Pressure Boundary Demin Water and AntifreezeCarbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Restricting Orifice Flow Restriction Demin Water and AntifreezeCarbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Demin Water and AntifreezeBrass Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Demin Water and AntifreezeBronze Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Demin Water and AntifreezeCarbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-45 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Demin Water and AntifreezeCast Iron Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies

Pressure Boundary Demin Water and AntifreezeStainless SteelLoss of Material Cracking Diesel Generator Maintenance Activities Lubricating Oil Subsystem The Lubricating Oil Subsystem table is added in response to Open Item 2.3.3.2-1 (b), SNC correspondence HL-6092, dated June 5, 2001. Filter Housing Pressure Boundary Lube Oil Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Heater Housing Pressure Boundary Lube Oil Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-46 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Heat Exchanger Shells Pressure Boundary Heat Transfer Lube Oil Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Piping/Tubing Pressure Boundary Lube Oil Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Piping/Tubing Pressure Boundary Lube Oil Copper Loss of Material Cracking Diesel Generator Maintenance Activities Pump Casing Pressure Boundary Lube Oil Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Strainer Casing Pressure Boundary Lube Oil Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Strainer Element Component Protection Lube Oil Carbon Steel Loss of Material Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Lube Oil Brass Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Lube Oil Bronze Loss of Material Cracking Diesel Generator Maintenance Activities

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-47 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Lube Oil Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Lube Oil Cast Iron Loss of Material Cracking Diesel Generator Maintenance Activities Heat Exchanger Components Containing Service Water or Air Subsystem The Heat Exchanger Components Containing Service Water or Air subsystem table is added in response to Open Item 2.3.3.2-1 (b), SNC correspondence HL-6092, dated June 5, 2001.

Bolting (applies to all three EDG subsystems) Pressure Boundary Moist Air Alloy Steel Loss of Material Loss of Preload Torque Activities Plant Coatings Program Bolting (applies to all three EDG subsystems) Pressure Boundary Moist Air Carbon Steel Loss of Material Loss of Preload Torque Activities Plant Coatings Program

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-48 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Heat Exchanger Shell Pressure Boundary Heat Transfer Moist Air Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Piping/Tubing Pressure Boundary Heat Transfer Raw Water Admiralty Brass Loss of Material Cracking Loss of Heat Exchanger Performance Diesel Generator Maintenance Activities Piping/Tubing Pressure Boundary Heat Transfer Raw Water Copper-Nickel Alloy Loss of Material Cracking Loss of Heat Exchanger Performance Diesel Generator Maintenance Activities Piping/Tubing Pressure Boundary Raw Water Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Piping/Tubing Pressure Boundary Raw Water Stainless SteelLoss of Material Cracking Diesel Generator Maintenance Activities

Table 2.3-12 Emergency Diesel Generator System [R43] - Aging Management Review Results

2.3-49 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Pump Casing Pressure Boundary Raw Water Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Raw Water Carbon Steel Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Raw Water Copper Loss of Material Cracking Diesel Generator Maintenance Activities Valve Bodies Pressure Boundary Raw Water Stainless SteelLoss of Material Cracking Diesel Generator Maintenance Activities

2.3-50 2.3.13 Cranes, Hoists and Elevators System [T31]

System Description The reactor building crane is the only inscope component for this system. The purpose of the reactor building crane is to provide the capability for moving major components for refueling operations and maintenance. The Unit 1 reactor building crane provides serv ice to both Unit 1 and Unit 2. Capability includes the handling of shield plugs, reactor vessel heads, drywell heads, steam dryers, steam separators, and the spent-fuel shipping cask. The reactor building crane main and auxiliary hooks have an electrical interlock system to prevent their potential movement over spent fuel.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.20 and Unit 2 FSAR Section 9.1.

2.3-51 Table 2.3-13 Cranes, Hoists and Elevators System [T31] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Structural Support Inside Carbon Steel Loss of Material Overhead Crane and Refueling Platform Inspection Structural Monitoring Program Protective Coatings Program Structural Monitoring Program was added in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

2.3-52 2.3.14 Tornado Vents System [T38]

System Description The purpose of the tornado vents is to act as blowout panels for venting the reactor and control building roofs under the following conditions: Against a wind velocity of 300 mph. When the internal static pressure in the building is increased to 55 lb/ft

2. When the temperature reaches approximately 212 °F. A rapid depressurization of air surrounding site structures can occur if a tornado funnel suddenly engulfs a structure. Venting is accomplished by placing blowout panels, designed to fail at a pressure lower than the safe building capability for internal pressure, to relieve excess pressure in all essential parts of such structures.

HNP FSAR References Additional information may be found in Unit 2 FSAR paragraph 3.3.2.3.

2.3-53 Table 2.3-14 Tornado Vents System [T38] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Screws Structural Support Inside Outside Stainless

Steel None None Required Support Frame Structural Support Inside Outside Aluminum None None Required Tornado Relief

Vent Dome Fission Product Barrier Inside Outside Acrylic (Plexiglas G Cellcast Acrylic Polymer) Cracking Structural Monitoring Program

2.3-54 2.3.15 Reactor Building HVAC System [T41]

System Description The purposes of the reactor building HVAC system are to: Provide an environment with controlled temperature and airflow to ensure the comfort and safety of operating personnel and to optimize equipment performance by the removal of the heat dissipated from the plant equipment. Promote air movement from operating areas and areas of lower airborne radioactivity potential to areas of greater airborne radioactivity potential prior to final filtration and

exhaust. Minimize the release of potential airborne radioactivity to the environment during normal plant operation by exhausting air, through a filtration system, from the areas in which a significant potential for radioactive particulates and/or radioiodine contamination exists. Provide a source of cooling to support the operation of the emergency core cooling systems (ECCS). Provide isolation capability to maintain secondary containment integrity and support operation of the standby gas treatment system (SGTS). The reactor building HVAC system utilizes a combination of air conditioning, heating, and once-through ventilation. Heat removal is provided by the ventilation air and by the chilled-water (Unit 2 only) and service-water cooling coils served by the reactor and radwaste building chilled water system and the plant serv ice water (PSW) system, respectively. Hot water heating coils, served by the plant heating system, are provided for heating.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.9 and Unit 2 FSAR subsection 9.4.2.

2.3-55 Table 2.3-15 Reactor Building HVAC System [T41] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Cooling Coil Tubing Pressure Boundary Raw Water Copper Alloy Loss of Material Cracking Loss of Heat Exchanger Performance PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Damper (frame only) Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Ductwork Pressure Boundary

Fission Product Barrier Air Galvanized Steel Cracking None Required Table 2.3-15 Reactor Building HVAC System [T41] - Aging Management Review Results

2.3-56 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Fan Housing Pressure Boundary Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Fan Inlet Housing Pressure Boundary Air Aluminum Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Fan Inlet Screen Protection from Debris Inside Aluminum Loss of Material Gas Systems Component Inspections Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Flow Element Pressure Boundary Air Stainless SteelCracking Gas Systems Component Inspections Tubing Pressure Boundary Air Copper Alloy Loss of Material Cracking Gas Systems Component Inspections

Table 2.3-15 Reactor Building HVAC System [T41] - Aging Management Review Results

2.3-57 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Component External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.3-58 2.3.16 Traveling Water Screens/Trash Racks System [W33]

System Description The purpose of the traveling water screens is to prevent debris from entering the portion of the intake structure from which the pumps take suction.

Larger debris are prevented from reaching the screens by the trash racks. The screen system is composed of two traveling screens, two motors, and two screen wash lines which operate in parallel to serve the common bay from which both the Unit 1 and Unit 2 pumps take suction. The specifications for both the trash racks and traveling screens require that they maintain their structural integrity following a design basis earthquake (DBE). Therefore, the pumps would continue to be protected from river debris by both the trash racks and the screens. The normal environment for the traveling screens and trash racks is submerged in river

water.

2.3-59 Table 2.3-16 Traveling Water Screens/Trash Racks System [W33] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Outside Carbon Steel Loss of Material Loss of Preload Torque Activities

Protective Coatings Program This line item added in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Trash Rack Debris Protection Submerged Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Traveling Screen Debris Protection Submerged Carbon Steel

Stainless Steel Loss of Material Structural Monitoring Program Traveling Screen Debris Protection Submerged Copper Alloy None None Required Valve Bodies Pressure Boundary Raw Water Carbon Steel Loss of Material

Flow Blockage Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program

Galvanic Susceptibility Inspections Component External Surfaces (< 200 °F) Pressure Boundary Outside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

Table 2.3-16 Hydrogen Control System - Aging Management Review Results 2.3-60 2.3-61 2.3.17 Outside Structures HVAC System [X41]

System Description The purpose of the intake structure HVAC system is to protect the intake structure equipment from adverse temperature conditions that could affect the reliability of the equipment. The diesel generator building HVAC system protects diesel generator building equipment from adverse temperature conditions that could affect the reliability of the equipment.

The river intake structure HVAC system consists of roof-mounted exhaust ventilators, gravity-operated louvers, and wall-mounted unit heaters. The ventilators are powered from separate power sources. Each ventilator has a separate control station and is operated by an individual thermostat. The independent controls are powered from the motor control center (MCC) control transformer for the associated fan. Since selected plant service water (PSW) pumps operate during normal and accident conditions in the plant, the thermostats and the individual fan control stations are located in the Unit 1 and Unit 2 PSW pump bay areas. The locations of the thermostats ensure the ventilation system is always activated when operation of the PSW pumps causes a heat buildup in the area. The unit heaters and their associated thermostats are strategically located at different areas of the building to provide adequate area coverage for maintaining the building above freezing temperatures.

The diesel generator rooms

' heating and ventilating systems consist of a power roof exhaust ventilator in each room for exhausting heat from the rooms when the generator is shut down and two 100% capacity power roof exhaust ventilators in each room for exhausting heat from the rooms during generator actuation. Two motor-operated wall air intake louvers, with fire dampers in each room, replenish the air removed by the exhaust ventilation. One louver serves as the air intake to the generator area; the other serves as the air intake to the battery rooms through the generator area.

HNP FSAR References Additional information about the system may be found in Unit 2 FSAR subsections 9.4.5 and

9.4.10.

2.3-62 Table 2.3-17 Outside Structures HVAC System [X41] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities Protective Coatings Program Bolting Pressure Boundary Outside Stainless SteelLoss of Preload Torque Activities Damper (frame only) Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001. Duct Sleeve Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Fan Housing Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001. Restricting

Orifices Pressure Boundary Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Tubing Pressure Boundary Air Copper Loss of Material Cracking Gas Systems Component Inspections

Table 2.3-17 Outside Structures HVAC System [X41] - Aging Management Review Results

2.3-63 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Unit Heater Housing Flow Direction Inside Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001. Component External Surfaces (< 200 °F) Pressure Boundary Inside Outside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.3-64 2.3.18 Fire Protection System [X43]

System Description The fire protection program assures, through a defense-in-depth design, that a fire will not prevent the necessary safe plant shutdown functions from occurring. Increases in the risk of radioactive releases to the environment could occur without the fire protection program. The program consists of detection and extinguishing systems, administrative controls and procedures, and trained personnel. The defense-in-depth principle is aimed at achieving an adequate balance in these areas along with: Preventing fires from starting, Detecting fires quickly, rapidly suppressing fires that occur and limiting their damage, and Designing plant safety systems so that a fire which starts in spite of the fire protection program and burns for a significant period of time will not prevent essential plant safety functions from being performed. Primary design consideration is given to locating redundant safe shutdown circuits and components in distinct areas separated by fire barriers which prevent the propagation of fire to adjacent areas. The barriers are designed to contain a design basis fire which totally involves the combustibles in the given area. A state-of-the-art, early warning fire detection multiplex system is utilized. The system is configured around master/slave concept linked to a common command center. All devices (e.g., detectors, tamper switches, pressure switches, etc.) are wired to their respective slave panels. Signals from each of these devices are grouped according to their originating detection zone. There are approximately 260 detection zones throughout both units. Water supply for the fire protection system inside the protected area is provided by two 300,000 gallon dedicated storage tanks. The tanks are supplied by two deep wells, each with a 700 gpm makeup pump, capable of refilling either tank within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. These water supplies are strained and filtered for normal makeup. There are three fire pumps, two diesel engine driven and one electric motor driven. Each pump is rated for 2500 gpm capacity at 125 psi. A single 70 gpm, 125 psig pressure maintaining pump (jockey pump) is provided to keep the system filled and pressurized during low flow draw offs and in the event of system leakage. Additional information may be found in the Hatch Fire Hazards Analysis (FHA).

2.3-65 Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Outside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Fire Damper Pressure Boundary Fire Barrier Air Carbon Steel Loss of Material Cracking Fire Protection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001. Fire Doors Fire Barrier Inside Carbon Steel Loss of Material Fire Protection Activities Fire Doors Fire Barrier Inside Galvanized Steel Copper Alloy

Stainless Steel Aluminum Nonmetallic, Inorganic

Gypsum Fibers, Nonasbestos Synthetic

Nonmetallic, Organic None None Required Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results

2.3-66 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Fire Hydrants Pressure Boundary Raw Water Cast Iron Loss of Material Cracking Flow BlockageFire Protection Activities Fittings Pressure Boundary Raw Water

Air Cast Iron Loss of Material

Cracking Flow BlockageFire Protection Activities Fittings Pressure Boundary Air Copper Alloy Cast Iron Loss of Material Cracking Fire Protection Activities Fusible Material Pressure Boundary Inside Nonferrous Metal Loss of Material Cracking Fire Protection Activities Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results

2.3-67 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Kaowool and Hold-Down Straps Fire Barrier Inside Galvanized Steel Insulation Material Loss of Material Change in Material Properties Fire Protection Activities Loss of Material was added as an AERM in response to RAI

3.4-FPS-9, SNC correspondence HL-6002 dated October 10, 2000.

Insulation Material was added and Cracking removed as an AERM in response to email from R.D. Baker to W.F.

Burton, dated April 21, 2000.

Nozzles Flow Restriction Air Copper Alloy Loss of Material Cracking Fire Protection Activities Flow blockage was removed as an AERM in response to RAI 3.4-FPS-8, SNC correspondence HL-6002 dated October 10, 2000. Nozzles Flow Restriction Air Aluminum

Copper Alloy Loss of Material Cracking Fire Protection Activities Penetration

Seals Fire Barrier Inside; Embedded Ceramics Carbon Steel Synthetic Fiber Elastomers Concrete Loss of Material Cracking Change in Material Properties Fire Protection Activities Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results

2.3-68 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Pilot Valves Pressure Boundary Raw Water Aluminum Loss of Material Cracking Flow BlockageFire Protection Activities Pipe Line Strainers Pressure Boundary Air Cast Iron Loss of Material Cracking Flow BlockageFire Protection Activities Piping Pressure Boundary Raw Water

Air Carbon Steel Aluminum Galvanized Steel Copper Alloy

Cast Iron Loss of Material Cracking Flow BlockageFire Protection Activities Piping Pressure Boundary Fuel Oil Carbon Steel Stainless Steel Loss of Material Cracking Diesel Fuel Oil Testing

Fire Protection Activities Piping Pressure Boundary Air Carbon Dioxide Dried Gas Carbon Steel Galvanized Steel Loss of Material Cracking Fire Protection Activities Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results

2.3-69 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Buried Cast Iron None None Required This line item was added in response to Open Item 3.1.13-1 (a), SNC correspondence HL-6092, dated June 5, 2001.

Pump Casings Pressure Boundary Raw Water Cast Iron Loss of Material

Cracking Flow BlockageFire Protection Activities Restricting

Orifices Pressure Boundary Flow Restriction Raw Water

Air Stainless SteelLoss of Material Cracking Flow BlockageFire Protection Activities Sprinkler Head Bulbs Pressure Boundary Inside Ceramics Cracking Fire Protection Activities Sprinkler Head Links Pressure Boundary Inside Copper Cracking Fire Protection Activities Loss of Material was removed as an AERM in response to

RAI 3.4-FPS-9, SNC correspondence HL-6002 dated October 10, 2000.

Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results

2.3-70 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Sprinkler Heads Flow Direction

Pressure Boundary Flow Restriction Raw Water

Air Stainless Steel Copper Alloy

Carbon Steel Loss of Material Cracking Flow BlockageFire Protection Activities Strainer Basket Pressure Boundary Raw Water

Air Stainless SteelLoss of Material Cracking Flow BlockageFire Protection Activities Strainers Pressure Boundary Air Raw Water Cast Iron Loss of Material Cracking Fire Protection Activities Flow blockage was removed as an AERM in response to

RAI 3.4-FPS-8, SNC correspondence HL-6002 dated October 10, 2000.

Tank Pressure Boundary Air Carbon Steel Loss of Material Cracking Fire Protection Activities Flow blockage was removed as an AERM in response to RAI 3.4-FPS-8, SNC correspondence HL-6002 dated October 10, 2000.

Tank Pressure Boundary Raw Water Carbon Steel Loss of Material Cracking Flow BlockageFire Protection Activities

Protective Coatings Program

Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results

2.3-71 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Tank Pressure Boundary Fuel Oil Carbon Steel Loss of Material Cracking Diesel Fuel Oil Testing

Fire Protection Activities Tank Pressure Boundary Carbon Dioxide Dried Gas Carbon Steel Loss of Material Cracking Fire Protection Activities Tank Insulation Environmental Control Inside Outside Organic Loss of Material Cracking Change in Material Properties Fire Protection Activities Loss of Material was added as an AERM and Outside was added as an Environment in response to RAI 3.4-FPS-9, SNC correspondence HL-6002 dated October 10, 2000.

Tubing Pressure Boundary Fuel Oil Copper Alloy Loss of Material

Cracking Diesel Fuel Oil Testing Fire Protection Activities Tubing Fittings Pressure Boundary Fuel Oil Raw Water Copper Alloy Cast Iron

Copper Loss of Material Cracking Diesel Fuel Oil Testing Fire Protection Activities Diesel Fuel Oil Testing was added in response to RAI 3.4-FPS-11, SNC correspondence HL-6002 dated October 10, 2000.

Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results

2.3-72 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Raw Water Air Carbon Steel Cast Iron

Copper Alloy Loss of Material Cracking Flow BlockageFire Protection Activities Valves Bodies Pressure Boundary Fuel Oil Copper Alloy Cast Iron Loss of Material Cracking Diesel Fuel Oil Testing

Fire Protection Activities Valves Bodies Pressure Boundary Carbon Dioxide Dried Gas Air Carbon Steel Copper Alloy Loss of Material Cracking Fire Protection Activities Component

External Surfaces (< 200 °F) Pressure Boundary Inside Outside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program Table 2.3-18 Fire Protection System [X43] - Aging Management Review Results

2.3-73 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Insulation Protect and Insulate Piping Outside Various Insulating Materials and Jacketing Loss of Material Cracking Change in Material Properties Equipment and Piping Insulation Monitoring Program FSAR 18.3.4, Equipment and Piping Insulation Program HL-6002, Sect. VI. B.2.4, Equipment and Piping Insulation Monitoring Program.

NUREG 1803, Sect. 3.1.21, Equipment and Piping Insulation Monitoring Program

2.3-74 2.3.19 Fuel Oil System [Y52]

System Description The purpose of the fuel oil system is to receive, store, and supply fuel oil to other systems.

Fuel oil is provided to the diesel generator system. Diesel engine fuel for Units 1 and 2 is stored in five interconnected buried tanks. Diesel fuel is transferred to the engine day tanks using dedicated, redundant transfer pumps and piping. The diesel fuel storage tanks are filled by gravity from a truck connection through a common header.

Two of the buried tanks are dedicated to each of the Unit 1 and Unit 2 diesel generators. The remaining tank is used to supply the swing diesel (1B) to serve either Unit 1 or Unit 2. The fuel oil system transfer pumps operate continuously on demand from the day tank level controllers. Storage tank levels are monitored and alarmed (low level) in the main control room (MCR).

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 8.4 and Unit 2 FSAR subsection 9.5.4.

2.3-75 Table 2.3-19 Fuel Oil System [Y52] - Aging Management Review Results

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Discharge Head Pressure Boundary Fuel Oil Carbon Steel Loss of Material Cracking Diesel Fuel Oil Testing Flex Hose Pressure Boundary Fuel Oil Stainless SteelLoss of Material Cracking Diesel Fuel Oil Testing Manway Shell Shelter/ Protection Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Piping Pressure Boundary Fuel Oil Carbon Steel Loss of Material Cracking Diesel Fuel Oil Testing Piping Pressure Boundary Fuel Oil Stainless SteelLoss of Material Cracking Diesel Fuel Oil Testing Table 2.3-19 Fuel Oil System [Y52] - Aging Management Review Results

2.3-76 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspection Passive Component Inspection Activities Piping Pressure Boundary Air Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections Piping Pressure Boundary Buried Carbon Steel with Coal Tar

Enamel Coating Loss of Material Protective Coatings Program This line item was added in response to Open Item 3.1.13-1 (a), SNC correspondence HL-6092, dated June 5, 2001.

Pump Pressure Boundary Fuel Oil Carbon Steel Loss of Material

Cracking Diesel Fuel Oil Testing Strainer Basket Shelter/

Protection Fuel Oil Stainless SteelLoss of Material Diesel Fuel Oil Testing Cracking was removed as an AERM in response to email from R.D. Baker to W.F.

Burton, dated June 20, 2000.

Tank Pressure Boundary Fuel Oil Carbon Steel Loss of Material Diesel Fuel Oil Testing Cracking was removed as an AERM in response to email from R.D. Baker to W.F. Burton, dated June 20, 2000.

Table 2.3-19 Fuel Oil System [Y52] - Aging Management Review Results

2.3-77 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fuel Oil Carbon Steel Loss of Material Cracking Diesel Fuel Oil Testing Valve Bodies Pressure Boundary Fuel Oil Stainless SteelLoss of Material Cracking Diesel Fuel Oil Testing Valve Bodies Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Valve Bodies Pressure Boundary Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Component

External Surfaces (< 200 °F) Pressure Boundary Inside Shelter / Protection Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.3-78 2.3.20 Control Building HVAC System [Z41]

System Description The control building HVAC system performs the following functions under normal and post accident conditions of the plant: Provides temperature control and air movement control, including a filtered fresh-air supply, for personnel comfort. Optimizes equipment performance by the removal of the heat dissipated from the plant equipment. Minimizes the potential of exhaust air entering into the supply air intake by exhausting at an elevated point via the reactor building vent plenum. Detects and limits the introduction of radioactive material into the main control room (MCR). The control building is served by both heating and air-conditioning (A/C) subsystems and a once-through ventilation subsystem. The A/C subsystems use direct expansion of chilled water cooling coils. Heating is provided by electric or hot water heating coils. The control room, computer room, water analysis room, chemistry laboratory and health physics area, and cold laboratory are the areas served by the heating and A/C subsystems. The low pressure coolant injection (LPCI) inverter room and Unit 2 vital A/C room are served by separate coolers. All other areas of the control building are served by a once-through

ventilation subsystem.

HNP FSAR References

For additional information see Unit 2 FSAR subsection 9.4.7.

2.3-79 Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results

Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Accumulator Air Valve Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Accumulator

Piping Pressure Boundary Dried Gas Carbon Steel Cracking None Required Accumulator Pressure Boundary Dried Gas Stainless SteelCracking None Required Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Condensing Unit Shell Pressure Boundary Inside Carbon Steel Loss of Material Cracking Protective Coatings Program This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Condensing Unit Shell Pressure Boundary Raw Water

Dried Gas Gray Cast IronLoss of Material Cracking PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results

2.3-80 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Condensing Unit Tubing Pressure Boundary Raw Water Copper Alloy Loss of Material Cracking

Loss of Heat Exchanger Performance PSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control Program This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Damper (frame only) Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Damper (frame only) Pressure Boundary Air Gray Cast IronLoss of Material Cracking Gas Systems Component Inspections Passive Component InspectionActivities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Duct Gasket Pressure Boundary Air Inside Fibers, Nonasbestos Synthetic

Elastomers, Other Material Property Changes Cracking Gas Systems Component Inspections Passive Component Inspection Activities Duct Heater Pressure Boundary Air Aluminum Loss of Material Gas Systems Component Inspections Duct Silencer Pressure Boundary Air Galvanized Steel Cracking None Required Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results

2.3-81 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Ductwork Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Ductwork Pressure Boundary Outside Galvanized Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Ductwork Flex Connector Pressure Boundary Air Inside Fibers, Non- Asbestos Synthetic

Elastomers, Other Material Property Changes Cracking Gas Systems Component Inspections

Passive Component InspectionActivities Fan Housing Pressure Boundary Air Wetted Aluminum Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Fan Housing Pressure Boundary Air Wetted Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results

2.3-82 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Fan Housing Pressure Boundary Air Wetted Galvanized Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Filter Housing Pressure Boundary Air Galvanized Steel Cracking None Required Fan Screen Protection from Debris Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Flow Element Pressure Boundary Air Stainless SteelCracking None Required This line item is added in response to Open Item 2.3.3.2-2 (a), (c), and (d), SNC correspondence HL-6092, dated June 5, 2001.

Instrument

Piping Pressure Boundary Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Instrument Piping Pressure Boundary Air Copper Alloy Loss of Material Cracking Gas Systems Component Inspections

Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results

2.3-83 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Louver Pressure Boundary Outside Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Piping Pressure Boundary Air Stainless SteelLoss of Material

Cracking Gas Systems Component Inspections Radiation Element Pressure Boundary Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Restricting

Orifice Pressure Boundary Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Thermowell Pressure Boundary Inside Stainless SteelCracking None Required Tubing Pressure Boundary Dried Gas Copper Cracking None Required Valve Bodies Pressure Boundary Dried Gas Carbon Steel Cracking None Required Valve Bodies Pressure Boundary Dried Gas Copper Alloy Cracking None Required Valve Bodies Pressure Boundary Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections

Table 2.3-20 Control Building HVAC System [Z41] - Aging Management Review Results

2.3-84 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Component External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

2.3-85 2.3.21 Turbine Building HVAC System [U41]

System Description The Turbine Building HVAC System performs the following functions under normal and post accident conditions of the plant: Provides temperature control and air movement control, including a filtered fresh-air supply, for personnel comfort. Optimizes equipment performance by the removal of heat dissipated from plant equipment. Provides for air movement from areas of lesser potential airborne radioactivity to areas of greater potential airborne radioactivity prior to final exhaust. Minimizes the possibility of exhaust air recirculation into the air intake. Minimizes the escape of potential airborne radioactivity to the outside atmosphere during normal operation by exhausting air through a suitable filtration system from the areas in which a significant potential for radioactive particulates and radioactive iodine contamination exists. Purges the Turbine Building area around the main control room to remove airborne radioactivity following a design basis loss of coolant accident, control rod drop accident, or main steam line break. Fresh air from outside is supplied to the Turbine Building by a duct system with two supply fans. Normally, one fan is in operation while the other is on standby. If the operating supply fan fails, the standby fan starts automatically. The normal outside air supply is filtered and tempered through a hot water heating coil. Air is exhausted from the Turbine Building by a duct system to the Reactor Building vent plenum by two exhaust fans. The Turbine Building exhaust is filtered by two 50% capacity filter trains. Each filter train consists of a bank of prefilters, carbon adsorbers, and HEPA filters. Only one of the two 100% capacity exhaust fans is normally in operation. If the operating exhaust fan fails, the standby fan starts automatically. Following a design basis loss of coolant accident, control rod drop accident, or main steam line break, leakage past the MSIVs is contained in the main steam piping downstream of the MSIVs and in the main condenser. One Turbine Building exhaust fan is manually placed in operation to purge the Turbine Building area around the main control room of any airborne radioactivity which might leak out of the main steam piping or main condenser in order to reduce the dose received by personnel in the main control room.

HNP FSAR References

More information about this system may be found in Unit 1 FSAR Section 10.9.3.4 and Unit 2 FSAR Section 9.4.4.

2.3-86 Table 2.3-21 Turbine Building HVAC System [U41] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program This line added for AST licensing amendments 256 (U1) and 200 (U2) Damper (frame only) Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line added for AST licensing amendments 256 (U1) and 200 (U2) Duct Gasket Pressure Boundary Air Inside Elastomers, Other Material Property Changes Cracking Gas Systems Component Inspections

Passive Component InspectionActivities This line added for AST licensing amendments 256 (U1) and 200 (U2) Ductwork Pressure Boundary Air Galvanized Steel Cracking None Required This line added for AST licensing amendments 256 (U1) and 200 (U2) Ductwork Flex Connector Pressure Boundary Air Inside Elastomers, Other Material Property Changes Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line added for AST licensing amendments 256 (U1) and 200 (U2) Fan Housing Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections

Passive Component InspectionActivities This line added for AST licensing amendments 256 (U1) and 200 (U2)

Table 2.3-21 Turbine Building HVAC System [U41] - Aging Management Review Results

2.3-87 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Filter Housing Pressure Boundary Air Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line added for AST licensing amendments 256 (U1) and 200 (U2) Flow Element Pressure Boundary Air Stainless SteelCracking None Required This line added for AST licensing amendments 256 (U1) and 200 (U2) Instrument Piping Pressure Boundary Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections This line added for AST licensing amendments 256 (U1) and 200 (U2) Piping Pressure Boundary Air Carbon Steel Loss of Material

Cracking Gas Systems Component Inspections

Passive Component InspectionActivities This line added for AST licensing amendments 256 (U1) and 200 (U2) Radiation

Element Pressure Boundary Air Stainless SteelLoss of Material Cracking Gas Systems Component Inspections This line added for AST licensing amendments 256 (U1) and 200 (U2) Tubing Pressure Boundary Air Copper Cracking None Required This line added for AST licensing amendments 256 (U1) and 200 (U2) Valve Bodies Pressure Boundary Air Cast Iron Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities This line added for AST licensing amendments 256 (U1) and 200 (U2)

Table 2.3-21 Turbine Building HVAC System [U41] - Aging Management Review Results

2.3-88 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Air Copper Alloy Cracking None Required This line added for AST licensing amendments 256 (U1) and 200 (U2) Component

External Surfaces (< 200 °F) Pressure Boundary Inside Carbon Steel Loss of Material Protective Coatings Program This line added for AST licensing amendments 256 (U1) and 200 (U2)

2.4-1 2.4 Steam And Power Conversion Systems The Steam and Power Conversion Systems are addressed in the following sections:

• Electro-Hydraulic Control System, Section 2.4.1

• Main Condenser System, Section 2.4.2 2.4.1 Electro-Hydraulic Control System [N32]

System Description The purpose of the electro-hydraulic control (EHC) system is to provide control of reactor pressure during reactor startup, power operation, and shutdown. EHC also provides a means of controlling main turbine speed and acceleration during turbine startup and protect the main turbine from undesirable operating conditions by initiating alarms, trips, and runbacks.

HNP FSAR References Additional information about this system may be found in Unit 1 FSAR Section 11.2 and Unit 2 FSAR subsection 10.2A.1.

2.4-2 Table 2.4-1 Electro-Hydraulic Control System [N32] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Reactor WaterStainless Steel Loss of Material

Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Valve Bodies Pressure Boundary Reactor WaterStainless Steel Loss of Material

Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections

2.4-3 2.4.2 Main Condenser System [N61]

System Description The main condenser provides a heat sink for turbine exhaust steam, turbine bypass steam, and other flows such as cascading heater drains, air ejector condenser drains, exhaust from the feed pump turbines, gland seal condenser, feedwater heater shell operating vents, and condensate pump suction vents. The main condenser also deaerates and provides storage capacity for the condensate water to be reused.

During plant operation, steam from the last-stage, low-pressure turbine is exhausted directly downward into the condenser shells through exhaust openings in the bottom of the turbine casings. The condenser serves as a heat sink for several others flows, such as exhaust steam from the feed pump turbines, cascading heater drains, air ejector condenser drain, gland-seal condenser drain, feedwater heater shell operating vents, and condensate pump suction vents.

Other flows occur periodically. These originate from condensate and reactor feed pump startup vents, reactor feed pump minimum recirculation flow, feedwater lines startup flushing, turbine equipment clean drains, low-point drains, extraction steam spills, makeup, and condensate.

During abnormal conditions, the condenser is designed to receive (not simultaneously) turbine bypass steam, feedwater heater high-level dumps, and relief valve discharge from feedwater heater shells, steam-seal regulator, and various steam supply lines.

During a design basis loss of coolant accident, control rod drop accident, or main steam line break, the main condenser and main steam piping downstream of the MSIVs are credited for a reduction in the offsite dose associated with leakage past the MSIVs.

Retention of MSIV leakage within these components provides for holdup and deposition of radionuclides. Also credited is an alternate leakage treatment path from the main steam lines downstream of the MSIVs to the condenser.

HNP FSAR References Additional information may be found in Unit 2 FSAR subsection 10.4.1.

2.4-4 Table 2.4-2 Main Condenser System [N61] - Aging Management Review Results Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Bolting Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Preload Loss of Material Torque Activities

Protective Coatings Program Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256. Condenser Shell Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material

Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections

Galvanic Susceptibility Inspections Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256. Piping Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material Cracking Reactor Water Chemistry Control Flow Accelerated Corrosion Program Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256.

Table 2.4-2 Main Condenser System [N61]- Aging Management Review Results 2.4-5 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material

Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections This row appears twice in the LRA and the duplicate was removed in response to RAI 3.5-MC-1, SNC correspondence HL-6002 dated October 10, 2000.

Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256.

Preheater Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Not applicable to Unit 1 Preheater Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Not applicable to Unit 1 Restricting Orifices Pressure Boundary Fission Product Barrier Reactor WaterStainless SteelLoss of Material

Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256.

Table 2.4-2 Main Condenser System [N61]- Aging Management Review Results 2.4-6 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Steam Traps Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material

Cracking Reactor Water Chemistry Control Flow Accelerated Corrosion Program Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Unit 2 Only Revised to remove Unit 1 components incorrectly added following implementation of Alternate Source Term License Amendment 256. See RER SNC460325. Strainer Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material Cracking Reactor Water Chemistry Control Flow Accelerated Corrosion Program Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256. Thermowell Pressure Boundary Fission Product Barrier Reactor WaterStainless Steel Loss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256.

VER 2.0 Table 2.4-2 Main Condenser System [N61]- Aging Management Review Results 2.4-7 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Valve Bodies Pressure Boundary Fission Product Barrier Reactor WaterCarbon Steel Loss of Material

Cracking Reactor Water Chemistry Control Flow Accelerated Corrosion Program Galvanic Susceptibility Inspections

Treated Water Systems Piping Inspections

Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256.

Component function of Fission Product Barrier added following implementation of Alternate Source Term license amendments 256 (U1) and 200 (U2) Valve Bodies Pressure Boundary

Fission Product Barrier Reactor WaterStainless Steel Loss of Material Cracking Reactor Water Chemistry Control Treated Water Systems Piping Inspections Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256.

Component function of Fission Product Barrier added following implementation of Alternate Source Term license amendments 256 (U1) and 200 (U2)

Table 2.4-2 Main Condenser System [N61]- Aging Management Review Results 2.4-8 Mechanical Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Component External Surfaces (< 200 °F) Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

Revised to include Unit 1 components following implementation of Alternate Source Term License Amendment 256.

2.5-1 2.5 Structures and Component Supports The Structures and Component Supports are addressed in the following sections:

• Piping Specialties, Section 2.5.1

• Conduits, Raceways, and Trays, Section 2.5.2

• Primary Containment, Section 2.5.3

• Fuel Storage, Section 2.5.4

• Reactor Building, Section 2.5.5

• Drywell Penetrations, Section 2.5.6

• Reactor Building Penetrations, Section 2.5.7

• Turbine Building, Section 2.5.8

• Intake Structure, Section 2.5.9

• Yard Structures, Section 2.5.10

• Main Stack, Section 2.5.11

• EDG Building, Section 2.5.12

• Control Building, Section 2.5.13

• Switchyard Structures, Section 2.5.14 2.5.1 Piping Specialties [L35]

System Description Piping specialties provide support for essential piping systems. Essential piping systems are required to maintain the integrity of safety-related and nonsafety-related systems during normal operations and transient/accident mitigation. These specialties include snubbers and pipe restraints regardless of system affiliation and also include non-ASME HVAC duct supports and tube trays.

2.5-2 Table 2.5-1 Piping Specialties [L35] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Hangers and Supports for ASME Class I Piping Structural Support Containment Atmosphere

Inside Carbon Steel Galvanized

Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Hangers and Supports for ASME Class I Piping Structural Support Containment Atmosphere

Inside Stainless SteelNone None Required Hangers and Supports for Non ASME Class I Piping, Tubing, and Ducts Structural Support Nonsafety Related Structural Support Containment Atmosphere Inside Outside Submerged Carbon Steel

Galvanized Steel Stainless Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Tube Trays and Covers Structural Support Nonsafety Related Structural Support Inside Outside Stainless SteelNone None Required

2.5-3 2.5.2 Conduits, Raceways, and Trays [R33]

System Description The purpose of the conduits, raceways, and trays system is to provide support for a cable system with cables and penetrations selected, routed, and located to survive the design basis events established for this plant and prevent a loss of function of any system due to a cable failure.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 8.8 and Unit 2 FSAR Section 8.3.

2.5-4 Table 2.5-2 Conduits, Raceways, and Trays [R33] - Aging Management Review Results

Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Cable Trays and supports Structural Support Nonsafety Related Structural Support Containment Atmosphere

Inside Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Cable Trays and supports Structural Support Nonsafety Related Structural Support Containment Atmosphere

Inside Aluminum None None Required

2.5-5 2.5.3 Primary Containment [T23]

System Description The purpose of the primary containment is to isolate and contain fission products released from the reactor primary system following a design basis accident (DBA) and to confine the postulated release of radioactive material.

The primary containment design employs a pressure suppression containment system which houses the reactor vessel, the reactor coolant recirculating loops, and other branch connections of the reactor primary system. The pressure suppression system consists of a drywell, a pressure suppression chamber (torus) which stores a large volume of water, a connecting vent system between the drywell and the pressure suppression pool, isolation valves, vacuum relief system, containment cooling systems, and other service equipment.

The pressure suppression chamber is a steel pressure vessel in the shape of a torus located below and encircling the drywell, with a major diameter of approximately 107 ft and a cross-sectional diameter of approximately 28 ft. The pressure suppression chamber contains the suppression pool and the air space above the pool. The suppression chamber transmits seismic loading to the reinforced concrete foundation slab of the reactor building. Space is provided outside of the chamber for inspection.

HNP FSAR References Additional information about this system may be found in Unit 1 FSAR subsection 5.1.2 and Unit 2 FSAR subsection 6.2.1.

2.5-6 Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Containment Atmosphere

Embedded Inside Torus Water Carbon Steel

Galvanized Steel Stainless Steel Loss of Material Protective Coatings Program

Inservice Inspection Program Suppression Pool Chemistry Control Bolting Pressure Boundary Containment Atmosphere Inside Carbon Steel Loss of Material Loss of Preload Protective Coatings Program

Torque Activities Line item added in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Blind Flange* Fission Product Barrier Torus Water Carbon Steel Loss of Material

Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Treated Water Systems Piping Inspections was added in response to email from R.D.

Baker to W.F. Burton, dated April 21, 2000.

Containment Isolation Valves* Fission Product Barrier Demin Water Stainless SteelLoss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Containment Isolation Valves* Fission Product Barrier Demin Water Carbon Steel Loss of Material Cracking Demineralized Water and Condensate Storage Tank Chemistry Control Treated Water Systems Piping Inspections

Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review

2.5-7 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Containment Isolation Valves* Fission Product Barrier Torus Water Carbon Steel Loss of Material Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Containment Isolation Valves* Fission Product Barrier Raw Water Carbon Steel Loss of Material

Cracking Passive Component Inspection Activities Containment Isolation Valves* Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Gas Systems Component Inspections Passive Component Inspection Activities Containment Isolation Valves* Fission Product Barrier Wetted Gas Stainless SteelLoss of Material

Cracking Gas Systems Component Inspection Containment Penetrations (Mechanical only) Fission Product Barrier Containment Atmosphere Embedded Inside Carbon Steel Stainless Steel Loss of Material Protective Coatings Program

Inservice Inspection Program

Primary Containment Leakage Rate Testing Program

Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review

2.5-8 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Miscellaneous Steel Structural Support Radiation Shielding

Nonsafety Related Structural Support Pipe Whip Restraint Containment Atmosphere

Embedded Inside High Humidity

Torus Water Carbon Steel Galvanized

Steel Loss of Material Protective Coatings Program

Inservice Inspection Program

Suppression Pool Chemistry Control Piping* Fission Product Barrier Demin Water Stainless SteelLoss of Material

Cracking Demineralized Water and Condensate Storage Tank Chemistry Control

Treated Water Systems Piping Inspections Piping* Fission Product Barrier Torus Water Carbon Steel Loss of Material Cracking Suppression Pool Chemistry Control Treated Water Systems Piping Inspections Piping* Fission Product Barrier Raw Water Carbon Steel Loss of Material

Cracking Passive Component Inspection Activities

Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review

2.5-9 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Piping* Fission Product Barrier Wetted Gas Carbon Steel Loss of Material Cracking Gas Systems Component Inspections Passive Component Inspection Activities Piping* Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Gas Systems Component Inspection Reinforced Concrete Structural Support Shelter/Protect ion Radiation Shielding

HE/ME Shielding

Missile Barrier

Fission Product Barrier Flood Barrier Containment Atmosphere

Inside Concrete Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review

2.5-10 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Steel Bellows (Inside Vent Pipe)

Pressure Boundary Fission Product Barrier Containment Atmosphere Inside Carbon Steel

Stainless Steel Loss of Material Protective Coatings Program

Inservice Inspection Program

Primary Containment Leakage Rate Testing Program

Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review

2.5-11 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Structural Support Shelter/Protect ion Pressure Boundary Radiation Shielding

Nonsafety Related Structural Support HE/ME Shielding

Missile Barrier Pipe Whip Restraint Fission Product Barrier Exchange Heat Containment Atmosphere

Embedded Inside Torus Water

Carbon Steel Stainless Steel Loss of Material Cracking Protective Coatings Program Primary Containment Leakage Rate Testing Program Inservice Inspection Program Suppression Pool Chemistry Control Component Cyclic or Transient Limit Program

Table 2.5-3 Primary Containment [T23] - Summary of Aging Management Review

2.5-12 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Tubing* Pressure Boundary Fission Product Barrier Wetted Gas Stainless SteelLoss of Material Cracking Gas Systems Component Inspections Vent Pipe, Vent Header, Downcomers Pressure Boundary Fission Product Barrier Containment Atmosphere

Inside High Humidity

Torus Water Carbon Steel Loss of Material Cracking Protective Coatings Program Inservice Inspection Program

Primary Containment Leakage Rate Testing Program

Component Cyclic or Transient Limit Program Suppression Pool Chemistry Control Component

External Surfaces (< 200 °F) Pressure Boundary Fission Product Barrier Inside Carbon Steel Loss of Material Protective Coatings Program FSAR 18.3.3, Protective Coatings Program

HL-6002, Sect. VI. B.2.3, Protective Coatings Program.

NUREG 1803, Sect. 3.1.20, Protective Coatings Program

• Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.

2.5-13 2.5.4 Fuel Storage [T24]

System Description The purpose of the fuel storage system is to provide specially designed underwater storage space for the spent-fuel assemblies which require shielding during storage and handling.

The fuel storage facility is located inside the secondary containment on the refueling floor.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.2, 10.3 and Unit 2 FSAR Section 9.1.

2.5-14 Table 2.5-4 Fuel Storage [T24] - Summary of Aging Management Review

Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Anchors and Bolts Structural Support Inside

Demin Water Stainless SteelLoss of Material Fuel Pool Chemistry Control The original line item was modified, creating two line items, in response to RAI 3.6-24, SNC correspondence HL-6002 dated October 10, 2000.

Anchors and Bolts Structural Support Embedded

Inside Stainless SteelLoss of Material Structural Monitoring Program Miscellaneous

Steel Structural Support Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Miscellaneous Steel Fission Product Barrier Inside Demin Water Stainless SteelLoss of Material Fuel Pool Chemistry Control The original line item was modified, creating two line items, in response to RAI 3.6-24, SNC correspondence HL-6002 dated October 10, 2000.

Miscellaneous

Steel Fission Product Barrier Embedded Inside Stainless SteelLoss of Material Structural Monitoring Program Table 2.5-4 Fuel Storage [T24] - Summary of Aging Management Review

2.5-15 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Reinforced Concrete Structural Support Shelter/Protect

ion Inside Concrete Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Reinforced Concrete Structural Support Nonsafety Related Structural Support Inside Concrete

Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Seismic restraints for spent fuel storage racks Structural Support Inside Demin Water Aluminum Loss of Material Fuel Pool Chemistry Control Storage Racks

- New Fuel Structural Support Nonsafety Related Structural Support Inside Aluminum None None Required This line item was added in response to RAIs 3.6-20 & 24, SNC correspondence HL-6002 dated October 10, 2000.

Storage Racks Structural Support Nonsafety Related Structural Support Inside Aluminum None None Required Table 2.5-4 Fuel Storage [T24] - Summary of Aging Management Review

2.5-16 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Structural Support Shelter/

Protection Fission Product Barrier Inside Demin Water Stainless SteelLoss of Material Fuel Pool Chemistry Control

2.5-17 2.5.5 Reactor Building [T29]

System Description The purpose of the reactor building is to shelter and support the refueling and reactor

servicing equipment, new and spent fuel storage facilities, and other reactor auxiliary and service equipment.

The building is a reinforced concrete structure with a steel superstructure. The building consists of the following major structural components: Reinforced concrete foundation mat. Reinforced concrete exterior walls and prestressed exterior wall panels. Reinforced concrete floors with reinforced concrete beams and girders framing. Reinforced concrete interior walls with some blockouts filled with concrete masonry. Reinforced concrete roof slab on metal roof deck system supported by steel superstructure. The reactor building completely encloses the reactor and its pressure suppression primary containment system. Also housed within the reactor building are the core standby cooling systems, reactor water cleanup demineralizer system, standby liquid control system, control rod drive system, reactor protection system, and electrical equipment components. The building is designed for minimum leakage so that the standby gas treatment system (SGTS) has the necessary capacity to reduce and hold the building at a subatmospheric pressure under normal wind conditions.

HNP FSAR References

Additional information may be found in Unit 1 FSAR subsection 12.2.1 and Unit 2 FSAR Section 3.0.

2.5-18 Table 2.5-5 Reactor Building [T29] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Inside

Outside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Blowout Panels Structural Support Fission Product Barrier Inside Aluminum None None Required Miscellaneous Steel Structural Support Nonsafety Related Structural Support HE/ME Shielding Inside Outside Carbon Steel Galvanized

Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

Table 2.5-5 Reactor Building [T29] - Aging Management Review Results 2.5-19 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Miscellaneous Steel Structural Support Nonsafety Related Structural Support HE/ME Shielding Inside Outside Stainless SteelNone None Required Panel Joint Seals and Sealants Shelter/ Protection Fission Product Barrier Inside Outside Elastomers; Nonmetallic, Inorganic Material Property Changes Cracking Loss of Adhesion Structural Monitoring Program Protective Coatings Program was removed in response to RAI 3.6-27, SNC correspondence HL-6002 dated October 10, 2000; and in response to email from R.D. Baker to W.F. Burton, dated April 21, 2000.

Table 2.5-5 Reactor Building [T29] - Aging Management Review Results 2.5-20 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Reinforced Concrete Structural Support Shelter/Protect

ion Radiation Shielding

Nonsafety Related Structural Support HE/ME Shielding Missile Barrier

Fission Product Barrier Flood Barrier

Fire Barrier Inside Outside Concrete Masonry Block

Carbon Steel Loss of Material Cracking Structural Monitoring Program

Protective Coatings Program

Table 2.5-5 Reactor Building [T29] - Aging Management Review Results 2.5-21 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Structural Support Nonsafety Related Structural Support Missile Barrier Inside Outside Submerged Carbon Steel

Galvanized Steel Stainless Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

Overhead Crane and Refueling Platform InspectionsOverhead Crane and Refueling Platform Inspections added in response to email from R.D. Baker to W.F.

Burton, dated April 21, 2000.

2.5-22 2.5.6 Drywell Penetrations [T52]

System Description The purpose of the drywell penetrations is to provide a path for cable currents/signals to pass through primary containment to support the various modes of operation of their associated systems while maintaining primary containment integrity.

Mechanical penetrations are discussed in Section 2.5.3 (Primary Containment [T23]).

Containment penetrations include electrical penetration assemblies in addition to the mechanical penetrations referenced above. Electrical penetrations are hermetically sealed penetrations which are welded to the primary containment shell plate. They must maintain their primary containment pressure integrity function during all postulated operating and accident conditions. They are designed for the same pressure and temperature conditions as the drywell and pressure suppression chamber.

HNP FSAR References For additional information see Unit 1 FSAR Section 5.2 and Unit 2 FSAR subsection 6.2.1.

2.5-23 Table 2.5-6 Drywell Penetrations [T52] - Aging Management Review Results

Structural Component Component Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Fission Product Barrier Containment Atmosphere

Embedded Inside Carbon Steel Loss of Material Protective Coatings Program

Primary Containment Leakage Rate Testing Program

Inservice Inspection Program

2.5-24 2.5.7 Reactor Building Penetrations [T54]

System Description The purpose of the reactor building penetrations is to allow mechanical and electrical equipment and personnel to pass through secondary containment to support the various modes of operation of their associated systems while maintaining secondary containment

integrity.

Penetrations for piping and ducts are designed for leakage characteristics consistent with containment requirements for the entire building. Electrical cables and instrument leads pass through ducts sealed into the building wall.

HNP FSAR References Additional information may be found in Unit 1 FSAR paragraph 5.3.3.2 and Unit 2 FSAR figure

8.3-11.

2.5-25 Table 2.5-7 Reactor Building Penetrations [T54] - Summary of Aging Management Review Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Fission Product Barrier Embedded

Inside Outside Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

2.5-26 2.5.8 Turbine Building [U29]

System Description The purpose of the turbine building is to house the turbine-generator and associated auxiliaries including the condensate and feedwater systems.

The turbine building is a steel and concrete structure consisting of the following major structural components: Reinforced concrete foundation mat. Reinforced concrete floors self-supporting or supported by structural steel framing. Reinforced concrete or concrete block interior walls. Reinforced concrete turbine pedestal resting on concrete mat foundation. Reinforced concrete exterior walls. Reinforced concrete slab on metal roof deck system supported by steel framing.

HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 12.2.2 and Unit 2 FSAR Section

3.2.

2.5-27 Table 2.5-8 Turbine Building [U29] - Aging Management Review Results

Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Embedded Inside Outside Wetting Other Than Humidity Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Miscellaneous Steel Structural Support Nonsafety Related Structural Support Inside Carbon Steel Galvanized

Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Reinforced Concrete Structural Support Shelter/Protect ion Radiation Shielding

Nonsafety Related Structural Support Buried Inside Outside Concrete Masonry Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

Table 2.5-8 Turbine Building [U29] - Aging Management Review Results 2.5-28 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Structural Support Shelter/Protect

ion Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program Protective Coatings Program

2.5-29 2.5.9 Intake Structure [W35]

System Description The purpose of the intake structure is to protect residual heat removal service water and plant service water equipment from the influence of environmental conditions such as flooding, earthquakes, and tornadoes.

The intake structure is a concrete and steel structure consisting of the following major structural components: Reinforced concrete foundation mat. Reinforced concrete exterior walls and internal walls. Reinforced concrete floors and roof. Structural steel framing and grating, steel water spray and internal missile shield barriers, stairs, and platforms.

Unit 1 shares the intake structure with Unit 2. The intake structure has labyrinth access openings for protection against tornado missiles.

HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 12.2.7 and Unit 2 FSAR

subsection 3.8.4.

2.5-30 Table 2.5-9 Intake Structure [W35] - Aging Management Review Results

Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Embedded Inside Outside High Humidity Wetting Other Than Humidity Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Miscellaneous Steel Structural Support Nonsafety Related Structural Support Missile Barrier

Embedded Inside Outside High Humidity Wetting Other Than Humidity

Submerged Carbon Steel

Galvanized

Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

Table 2.5-10 Yard Structures [Y29] - Aging Management Review Results

2.5-31 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Reinforced Concrete Structural Support Shelter/Protect

ion Nonsafety Related Structural Support Missile Barrier

Flood Barrier Buried Inside Outside High Humidity Wetting Other Than Humidity

Submerged Concrete Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Structural

Steel Structural Support Shelter/Protect ion Nonsafety Related Structural Support Missile Barrier Flow Direction

Embedded

Inside Outside High Humidity Wetting Other Than

Humidity Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

2.5-32 2.5.10 Yard Structures [Y29]

System Description The purpose of the yard structures is to provide equipment integrity and personnel habitability for various structures on the plant site.

Some of the structures included in Y29 are: The concrete wall and foundation accommodating the condensate storage tank. The foundation of the nitrogen storage tank. The service water valve pit boxes. The foundation for the fire pump house. The foundations for the two fire protection water storage tanks. The foundations for the two fire protection diesel pump fuel tanks. Underground concrete duct runs and pull boxes between Class I structures.

HNP FSAR References Additional information may be found in Unit 1 FSAR paragraph 5.2.3.9 and Unit 2 FSAR paragraph 3.8.5.1.

2.5-33 Table 2.5-10 Yard Structures [Y29] - Aging Management Review Results

Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Inside Outside Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Cover Plates -

Pull Boxes Shelter/Protect

ion Flood Barrier Inside Outside Aluminum None None Required Miscellaneous Steel Structural Support Nonsafety Related Structural Support Inside Outside Carbon Steel Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Reinforced Concrete Structural Support Nonsafety Related Structural Support Inside Outside Concrete Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

Table 2.5-10 Yard Structures [Y29] - Aging Management Review Results

2.5-34 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Structural Support Shelter/Protect

ion Nonsafety Related Structural Support Inside Outside Carbon Steel Loss of Material Structural Monitoring Program Protective Coatings Program

2.5-35 2.5.11 Main Stack [Y32]

System Description The purpose of the main stack is to support and protect monitoring equipment and provide for the monitoring and elevated release of gaseous effluents from the main stack system.

The main stack is a concrete cylindrical shape which consists of the following major

components: Reinforced concrete foundation mat supported on steel "H" piles. Reinforced concrete truncated conical cylinder. Reinforced concrete internal floors. Reinforced concrete loading bay consisting of concrete base slab, external and internal walls, and roof. Unit 1 shares a single main stack used to discharge gaseous waste with Unit 2. The main stack extends 120 meters above ground level.

HNP FSAR References

Additional information may be found in Unit 1 FSAR subsection 5.3.4 and Unit 2 FSAR Section 11.3.

2.5-36 Table 2.5-11 Main Stack [Y32] - Aging Management Review Results

Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Embedded Outside Galvanized

Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Anchors and Bolts Structural Support Nonsafety Related Structural Support Embedded Inside Outside Stainless Steel

Copper Alloy (Bronze) None None Required Miscellaneous Steel Structural Support Nonsafety Related Structural Support Outside Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Miscellaneous Steel Structural Support Nonsafety Related Structural Support Inside Galvanized Steel None None Required Table 2.5-11 Main Stack [Y32] - Aging Management Review Results 2.5-37 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Reinforced Concrete Structural Support Shelter/

Protection Radiation Shielding

Nonsafety Related Structural Support Fission Product Barrier Fire Barrier Inside Outside Concrete Carbon Steel

Masonry Block Loss of Material Cracking Structural Monitoring Program

Protective Coatings Program Fire Barrier was added as an intended function and Masonry Block added as a Material in response to RAI 3.4-FPS-13, SNC correspondence HL-6002 dated October 10, 2000.

Structural Steel Structural Support Nonsafety Related Structural Support Inside Galvanized Steel None None Required

2.5-38 2.5.12 EDG Building [Y39]

System Description

The purpose of the diesel generator building is to house the emergency diesel generators (EDG) and their accessories for safe plant shutdown for both Unit 1 and Unit 2.

The diesel generator building is a reinforced concrete structure consisting of the following major structural components: Reinforced concrete foundation mat. Reinforced concrete exterior walls and interior walls. Reinforced concrete roof and parapet wall. The diesel generator building houses EDGs and their accessories. The diesel generator building has labyrinth access openings for protection against tornado missiles. The diesel generator building is designed as a Seismic Category I structure to protect vital equipment and systems both during and following the most severe natural phenomena.

HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 12.2.6 and Unit 2 FSAR subsection 9.4.5.

2.5-39 Table 2.5-12 EDG Building [Y39] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Miscellaneous

Steel Structural Support Nonsafety Related Structural Support Embedded Inside Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Reinforced Concrete Structural Support Shelter/Protect ion Nonsafety Related Structural Support Missile Barrier Inside Outside Concrete

Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

Table 2.5-12 EDG Building [Y39] - Aging Management Review Results 2.5-40 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Structural Steel Structural Support Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

2.5-41 2.5.13 Control Building [Z29]

System Description The purpose of the control building is to house the common control room for Units 1 and 2 and associated auxiliaries.

The building is a reinforced concrete structure with steel framing. The building consists of the

following major structural components. Reinforced concrete foundation mat. Reinforced concrete floors with reinforced concrete beam and girder framing. Reinforced concrete or concrete block interior walls and reinforced concrete columns. Reinforced concrete exterior walls and prestressed exterior wall panels. Reinforced concrete slab on metal roof deck system supported by steel framing.

HNP FSAR References

Additional information may be found in Unit 1 FSAR paragraph 12.3.3.1.1 and Unit 2 FSAR subsection 3.2.1.

2.5-42 Table 2.5-13 Control Building [Z29] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Structural Support Nonsafety Related Structural Support Embedded

Inside Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Blowout Panels Structural Support Fission Product Barrier Inside Aluminum None None Required Miscellaneous Steel Structural Support Nonsafety Related Structural Support Embedded Inside Carbon Steel Galvanized

Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

Table 2.5-13 Control Building [Z29] - Aging Management Review Results

2.5-43 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Reinforced Concrete Structural Support Shelter/

Protection Nonsafety Related Structural Support Missile Barrier

Fire Barrier Inside Outside Concrete Carbon Steel

Masonry Block Loss of Material Cracking Structural Monitoring Program

Protective Coatings Program Fire Barrier was added as an intended function and Masonry Block added as a Material in response to RAI 3.4-FPS-13, SNC correspondence HL-6002 dated October 10, 2000.

Structural

Steel Structural Support Shelter/Protect ion Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

2.5-44 2.5.14 Switchyard Structures [S48]

System Description The purpose of the switchyard structures is to provide equipment integrity and personnel habitability for structures in the low voltage and high voltage switchyards which are required to attach the onsite AC power distribution system to the offsite power system and energize the safety-related AC buses.

Some of the structures included in S48 are: The foundations of station service transformers 1C, 1D, 2C, and 2D. The foundations for structures such as 230 kV line towers, breakers, switch structures, and bus support columns. The foundation and structure of the switchhouse. Underground concrete duct runs and covers.

HNP FSAR References Additional information may be found in Unit 2 FSAR paragraph 8.3.

2.5-45 Table 2.5-14 Switchyard Structures [S48] - Aging Management Review Results

Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Anchors and Bolts Nonsafety Related Structural Support Inside Outside Embedded Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Added due to LR-ISG-02 per RIS 2007-16, Rev. 1 Cable Trays and supports Nonsafety Related Structural Support Inside Outside Carbon Steel Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Added due to LR-ISG-02 per RIS 2007-16, Rev. 1 Cable Trays and supports Nonsafety Related Structural Support Inside Outside Aluminum None None Required Added due to LR-ISG-02 per RIS 2007-16, Rev. 1 Miscellaneous

Steel Nonsafety Related Structural Support Inside Outside Carbon Steel

Galvanized Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Added due to LR-ISG-02 per RIS 2007-16, Rev. 1 Reinforced Concrete Nonsafety Related Structural Support Inside Outside Concrete

Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Added due to LR-ISG-02 per RIS 2007-16, Rev. 1 Structural Steel Shelter/Protect

ion Nonsafety Related Structural Support Inside Outside Carbon Steel Galvanized

Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Added due to LR-ISG-02 per RIS 2007-16, Rev. 1

2.6-1 2.6 Electrical Components The Electrical Components for the Plant Hatch LRA Systems are addressed in the following sections:

• Electric Power and Instrumentation and Controls (Plant Wide), Section 2.6.1 o Analog Transmitter Trip System, Section 2.6.1(a) o Nuclear Steam Supply Shutoff System, Section 2.6.1(b) o Primary Containment Isolation System, Section 2.6.1(c) o Reactor Protection System, Section 2.6.1(d) o Remote Shutdown System, Section 2.6.1(e) o Process Radiation Monitoring System, Section 2.6.1(f) o Heat Trace System, Section 2.6.1(g) o Plant AC Electrical System, Section 2.6.1(h) o DC Electrical System, Section 2.6.1(i) o Plant Communications System, Section 2.6.1(j) o Power Transformers System, Section 2.6.1(k) o Emergency Response Facilities System, Section 2.6.1(l)

• Electrical Panels, Racks, & Cabinets, Section 2.6.2

• Instruments Racks, Panels, & Enclosures, Section 2.6.3

• Switchyard, Section 2.6.4 2.6.1 Electric Power and Instrumentation and Controls (Plant Wide)

The Electric Power and Instrumentation and Controls LRA system is comprised of several plant systems as described in Sections 2.6.1(a) - 2.6.1(l) below.

Table 2.6-1 presents the electrical AMR results. The list of electrical components subject to an AMR is determined on a plantwide basis by compiling a list of all electrical component types installed in the plant, then applying the scoping and screening criteria in the Rule to determine those component types subject to an AMR. The resulting list is an encompassing list of component types, not individual components. For example, cable is listed as a component type. Individual circuits are not evaluated to determine whether they are in scope. The list of component types subject to an aging management review has been further reduced by application of the scoping criteria to the component types which meet the screening criteria. These criteria are found in 10 CFR 54.4(a). Any component type which does not meet the scoping criteria in this section on a generic basis does not require an aging m anagement review. The comprehensive list of electrical component types is included in Table 2.6-1.

2.6-2 2.6.1(a) Analog Transmitter Trip System [A70]

System Description

The purpose of the analog transmitter trip system (ATTS) is to monitor several critical plant parameters and provide actuation and trip signals to the following systems: Reactor Protection System Primary Containment Isolation System Secondary Containment Isolation System Core Spray System Residual Heat Removal System High Pressure Coolant Injection System Reactor Core Isolation Cooling Automatic Depressurization System Low-Low Set Logic Alternate Rod Insertion Logic Reactor Recirculation System Emergency Diesel Generators Safety Relief Valves The ATTS is a solid-state electronic trip system designed to provide monitoring of process parameters. The system consists of primary sensors, master trip assemblies, slave trip assemblies, calibration units, card file assemblies, and other accessories.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.18 and Unit 2 FSAR Section 7.8.

2.6-3 2.6.1(b) Nuclear Steam Supply Shutoff System [A71]

System Description The purpose of the nuclear steam supply shutoff system is to isolate the reactor vessel and various other systems which carry radioactive fluids within the primary containment to prevent the release of radioactive materials.

Sensor elements are located in the reactor vessel, drywell, main steam lines (MSLs), MSL pipe chase, turbine building, the reactor water cleanup (RWCU) system, and areas around the RWCU system. The system functions are initiated when sensors actuate and provide input to relay control circuits, which in turn initiate the closure of containment isolation valves and initiate various other functions. The other functions include annunciation, post accident monitoring system recorder chart speed control, control room pressurization, and signal input to the primary containment isolation system.

HNP FSAR References Additional information may be found in Unit 1 FSAR subsection 7.3.4 and Unit 2 FSAR subsection 7.3.2.

2.6.1(c) Primary Containment Isolation System [C61]

System Description

The purpose of the primary containment isolation system (PCIS) is to limit fission product releases by isolating fluid systems during accident/transient conditions.

The PCIS functions are initiated when sensors monitoring critical parameters activate and provide input to relay control circuits which in turn initiate closure of containment isolation valves or initiate various other functions. The other functions include initiating SGTS, isolating reactor building ventilation, isolating refueling floor ventilation, and isolating the off-gas system exhaust.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.3 and Unit 2 FSAR subsection 7.3.2.

2.6-4 2.6.1(d) Reactor Protection System [C71]

System Description The purpose of the reactor protection system (RPS) is to provide protection against the onset and consequences of conditions that challenge the integrity of the fuel barriers and the nuclear system process barrier by the initiation of an automatic scram.

The RPS is composed of two independent, dual c hannel monitor/trip systems, associated process system sensors, and annunciators. The RPS is designed to initiate a reactor scram to: Preserve the integrity of fuel cladding. Preserve the integrity of the reactor coolant pressure boundary (RCPB). Minimize the energy released during a loss-of-coolant accident (LOCA).

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.2 and Unit 2 FSAR Section 7.2.

2.6.1(e) Remote Shutdown System [C82]

System Description The remote shutdown panels provide controls and indications to safely shut down the reactor for a selected number of components in a select ed number of systems in the event the control room becomes uninhabitable.

2.6.1(f) Process Radiation Monitoring System [D11]

System Description The purpose of the process radiation monitoring system is to provide input into the reactor

protection system, primary containment isolation system, and others for system isolation.

HNP FSAR References More information on this system can be found in Unit 1 FSAR Section 7.12 and Unit 2 FSAR Section 11.4.

2.6-5 2.6.1(g) Heat Trace System [G13]

System Description The purpose of the heat trace system is to maintain piping, instrumentation, and equipment in working order during below freezing temperatures. A primary function is to maintain the sodium pentaborate solution in the standby liquid control system at a temperature high enough to prevent precipitation and solidification of the solution.

Standby liquid control storage tank temperature is maintained by adjusting the storage tank heater-indicating controller to maintain temperature control and prevent precipitation of the sodium pentaborate from solution. Thermostat controlled heat tracing is run along the pump suction piping to maintain suction piping solution temperature. A temperature versus concentration curve is monitored to ensure that sufficient margin will be maintained above saturation temperature.

HNP FSAR References

Additional information may be found in Unit 2 FSAR paragraph 4.2.3.4.2.

2.6.1(h) Plant AC Electrical System [R20]

System Description The entire auxiliary power distribution syst em, station service, and emergency service systems consisting of both 1E and Non-1E systems, distribute power to all ac auxiliaries required to startup, operate, and shut down the plant.

The emergency service portion Class 1E distributes power to all loads essential to plant safety and normal plant operation ensuring power is available to perform a safe plant

shutdown.

The auxiliary power distribution system distributes power to all auxiliaries necessary for normal plant operation.

The station auxiliary ac power system is divided into two portions: one for normal Non-Class 1E service and one for emergency Class 1E service. The emergency service portion distributes ac power required to shut down the reactor, maintain the shutdown condition, and operate all safety-related equipment necessary to mitigate the consequences of major accident conditions. The entire station aux iliary ac power system, both normal and emergency service portions, distributes power to all ac auxiliaries required to start up, operate, and shut down the plant.

HNP FSAR References

2.6-6 Additional information may be found in Unit 1 FSAR Sections 8.3 and 8.7 and Unit 2 FSAR subsection 8.3.1.

2.6-7 2.6.1(i) DC Electrical System [R42]

System Description The purpose of the dc distribution system is to provide reliable power from a rectified ac source (battery charger) with a battery backup to supply dc loads, control power, logic power, and inverters for all operational modes.

The battery system provides an uninterruptible source of power to normal Non-Class 1E and emergency Class 1E loads such as motors, circuit breaker controls, operation of logic and control relays, emergency lighting, etc. The emergency power is required to safely shutdown the reactor, maintain the reactor in a shutdown condition, and operate all auxiliaries necessary for plant safety under all plant operational modes.

The dc electrical system includes the following: 125/250 V station battery system Class 1E 125 V diesel generator battery system Class 1E 125 V cooling tower battery system Non-Class 1E 24/48 V instrumentation battery system Non-Class 1E Battery for 120/240 V vital ac system Non-Class 1E HNP FSAR References

Additional information may be found in Unit 1 FSAR Section 8.5 and Unit 2 FSAR subsection 8.3.2.

2.6-8 2.6.1(j) Plant Communications System [R51]

System Description The purpose of the plant communications system is to allow key personnel to communicate information about plant conditions and other pertinent information.

The intrasite communication system consists of a public address system; a private, dial telephone system; and a two-way radio communication system provided for paging and communication. The public address system which consists of handsets, amplifiers, loudspeakers, multi-tone generator, and associated equipment provides convenient, effective paging, and private conversational service. The private, automatic exchange dial telephone system is an electronic system of modular design utilizing stored program control and time division switching. A separate, two-way radio communication is provided to permit communication with mobile units and base stations within the range of the plant.

HNP FSAR References Additional information may be found in Unit 1 FSAR Section 10.15 and Unit 2 FSAR subsection 9.5.2.

2.6.1(k) Power Transformers System [S11]

System Description The in scope components for this system are the CD transformers. The function of these transformers is to provide power to 600V busses C or D from 4160V bus F during station blackout.

The transformers operate by dropping the voltage from 4160 volts to 600 volts.

HNP FSAR References

Additional information may be found in Unit 1 FSAR Section 8.3 and Unit 2 FSAR Section 8.3.

2.6-9 2.6.1(l) Emergency Response Facilities System [X75]

System Description The purpose of the emergency response facilities is to help the plant operators, shift technical advisors, supervisory personnel, and the NRC in rapidly assessing the plant safety status during normal, transient, and accident conditions.

The NRC-emergency response data system (NRC-ERDS) is the response to the ERDS Rule published in 10 CFR 50 in 1991. It is used during an Alert emergency classification or higher to transmit certain data to the NRC operations center in Rockville, Maryland. The X75 system includes the safety parameter display system (SPDS), the technical support center (TSC) HVAC system, and the ERDS.

HNP FSAR References

For additional information see Unit 1 FSAR Section 7.21 and Unit 2 FSAR Section 7.9.

2.6-10 This Page Intentionally Left Blank.

2.6-10 Table 2.6-1 Electrical Components [Plant Wide] - Aging Management Review Results Electrical Component Intended Function EnvironmentMaterial Aging EffectsAging Management Programs Comments Cable (Outside Containment)

Provide insulation resistance to preclude shorts, grounds, and unacceptable leakage currents Inside Outside Submerged Various Polymers Tinned and Bare Copper Change in Insulation Resistance Wetted Cable Activities Insulated Cables and Connections Program The Insulated Cables and Connections Program was added to this line item in response to Draft Open Item 51 (3.7.2.2-2), SNC correspondence HL-6037, dated January 31, 2001. Cable (Inside Containment)

Provide insulation resistance to preclude shorts, grounds, and unacceptable leakage currents Inside Various Polymers Tinned and Bare Copper None Insulated Cables and Connections Program The Insulated Cables and Connections Program was added to this line item in response to Draft Open Item

51 (3.7.2.2-2), SNC correspondence HL-6037, dated January 31, 2001. Electrical Connectors

Splices, Terminal Blocks Provide insulation resistance to preclude shorts, grounds, and unacceptable leakage currents Inside

Outside Various Polymers Galvanized and Stainless

Steel Tinned and Bare Copper None None

Table 2.6-1 Electrical Components [Plant Wide] - Aging Management Review Results

2.6-11 Electrical Component Intended Function EnvironmentMaterial Aging EffectsAging Management Programs Comments Electrical Penetration Assemblies Provide insulation resistance to preclude shorts, grounds, and unacceptable

leakage currents Inside Various Polymers Painted Steel

Stainless SteelNone None

(Penetration assemblies are covered by an EQ TLAA.)

Phase Bussing Provide insulation resistance to preclude shorts, grounds, and unacceptable leakage currents Inside Various Polymers Galvanized and Stainless

Steel Tinned and Bare Copper None None Nelson Frames Fission Product Barrier Fire Protection Inside Various Polymers Galvanized and Painted Steel None None

2.6-12 2.6.2 Electrical Panels, Racks, & Cabinets [H11]

System Description The purpose of the main control boards is to provide display, recording, and alarm to enable plant operators to monitor and control the equipment necessary for normal operations and transient/accident mitigation. H11 as described in this Specification includes only the supporting panels, racks, and cabinets.

HNP FSAR References

Additional information may be found in Unit 1 FSAR Section 7.16 and Unit 2 FSAR Section 3.2.

2.6-13 Table 2.6-2 Electrical Panels, Racks, & Cabinets [H11] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Electrical panels, racks and cabinets Structural Support Shelter/Protect ion Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program Protective Coatings Program

2.6-14 2.6.3 Instrument Racks, Panels, & Enclosures [H21]

System Description The purpose of the auxiliary control panels is to provide system information and control to allow operators to operate equipment from outside the main control room (MCR) in the reactor building, turbine building, and other auxiliary buildings.

The actual controls for each system are included in specific functions for the respective system. HNP FSAR References Additional information may be found in Unit 1 FSAR Section 7.16 and Unit 2 FSAR Section

3.10.

2.6-15 Table 2.6-3 Instrument Racks, Panels, & Enclosures [H21] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Instrument racks, panels and enclosures Structural Support Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program

2.6-16 2.6.4 Switchyard [S40]

System Description The high voltage switchyard consists of two sections, a 500 kV switchyard and a 230 kV switchyard. A 500/230 kV autotransformer connects the 500 kV switchyard to the 230 kV switchyard. The transmission network interconnections at HNP consist of four 500 kV lines and four 230 kV lines.

The low voltage (24 kV) switchyard contains one main transformer for each unit, unit auxiliary transformers 1A, 1B , 2A, and 2B, and startup auxiliary transformers 1C, 1D, 2C, and 2D. Offsite power is supplied from the high voltage switchyard to the startup auxiliary transformers via three physically independent 230 kV circuits. The startup auxiliary transformers then supply power to the safety related portion of the onsite distribution system.

A switchhouse containing relaying and controls is provided in the high voltage switchyard.

This section has been added in response to the 10 CFR 54.37(b) review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event.

HNP FSAR References Additional information may be found in Unit 2 FSAR Section 8.2.

2.6-17 Table 2.6-4 Switchyard [S40] - Aging Management Review Results Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Cable (Outside Containment)

Provide insulation resistance to preclude shorts, grounds, and unacceptable leakage currents Inside Outside Various Polymers Tinned and Bare Copper Change in Insulation Resistance Wetted Cable Activities

Insulated Cables and Connections Program Added in response to the 10 CFR 54.37(b) review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event. Electrical Connectors, Splices, Terminal Blocks Provide insulation resistance to preclude shorts, grounds, and unacceptable leakage currents Inside Outside Various Polymers Galvanized and Stainless Steel Tinned and Bare Copper None None Added in response to the 10 CFR 54.37(b) review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event. High-Voltage Insulators Insulate and support an electrical conductor Outside Porcelain, Malleable Iron, Galvanized Steel, Cement None None Added in response to the 10 CFR 54.37(b) review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event. Instrument racks, panels and enclosures Structural Support Nonsafety Related Structural Support Inside Carbon Steel Loss of Material Structural Monitoring Program

Protective Coatings Program Added in response to the 10 CFR 54.37(b) review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event.

2.6-18 Structural Component Intended Functions EnvironmentMaterial Aging EffectsAging Management Programs Comments Switchyard Bus and Connections Provide Electrical Connections Outside Aluminum, Copper, Bronze, Stainless

Steel, Galvanized Steel None None Added in response to the 10 CFR 54.37(b) review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event. Transmission Conductors

and Connections Provide Electrical Connections Outside Aluminum, Steel None None Added in response to the 10 CFR 54.37(b) review of NRC Regulatory Issue Summary (RIS) 2007-16, Revision 1, relating to LR-ISG-02 concerning recovery from a station blackout (SBO) event.

3-1 3 REFERENCES 3.1 Edwin I. Hatch License Renewal Docket 3.1.1 SNC Letter HL-5853, "Edwin I. Hatch Nuclear Plant Units 1 and 2, Application for License Renewal," dated February29, 2003. 3.1.2 SNC Letter HL-5979, "Edwin I. Hatch Nuclear Plant Units 1 and 2, Response to License Renewal Requests for Additional Information," dated August 29, 2000. 3.1.3 SNC Letter HL-6002, "Edwin I. Hatch Nuclear Plant Units 1 and 2, Response to License Renewal Requests for Additional Information," dated October 10, 2000. 3.1.4 SNC Letter HL-6024, "Edwin I. Hatch Nuclear Plant Units 1 and 2, Annual Update of License Renewal Application," dated December 15, 2000. 3.1.5 SNC Letter HL-6037, "Edwin I. Hatch Nuclear Plant, Transmittal of Responses to License Renewal Draft Open Items," dated January 31, 2001. 3.1.6 SNC Letter HL-6092, "Edwin I. Hatch Nuclear Plant Units 1 and 2, License Renewal Draft SER Open Items," dated June 5, 2001. 3.1.7 SNC Letter HL-6123, "Edwin I. Hatch Nuclear Plant Units 1 and 2, Transmittal of Additional Information for License Renewal Draft Safety Evaluation Report Open Items," dated September 5, 2001. 3.1.8 SNC Emails from R.D. Baker to W.F.Burton, dated April 21, 2000 through October 13, 2001 (Attachment C). 3.1.9 E.I. Hatch Final Safety Analysis Report, Chapter 18.

3.2 NRC References 3.2.1 10 CFR 54, The License Renewal Rule.

3.2.2 NUREG 1803, Rev. 1; Safety Evaluation Related to the License Renewal of the Edwin I. Hatch Nuclear Plant, Units 1 and 2. 3.2.3 RIS 2007-16, Revision 1: Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses 3.3 Other References 3.3.1 NMP-ES-063, License Renewal Program 3.3.2 NMP-ES-063-001, License Renewal Program Implementation Instructions 3.3.3 NMP-ES-063-003, 10 CFR 54.37(b) Review Instructions 3.3.4 NMP-ES-063-003-F01, 10 CFR 54.37(b) Review Form 3.3.5 NMP-ES-063-004, 10 CFR 54.37(b) Scoping Determination Instructions 3-2 3.3.6 NMP-ES-063-004-F01, 10 CFR 54.37(b) Scoping Determination Form 3.3.7 NMP-ES-063-005, 10 CFR 54.37(b) Commodity Evaluation Instructions 3.3.8 NMP-ES-063-005-F01, 10 CFR 54.37(b) Commodity Evaluation Form 3.3.9 NMP-ES-063-006, 10 CFR 54.37(b) Aging Management Review Evaluation Instructions 3.3.10 NMP-ES-063-006-F01, 10 CFR 54.37(b) AMR Evaluation Form 3.3.11 NMP-ES-063-007, 10 CFR 54.37(b) TLAA Evaluation Instructions 3.3.12 NMP-ES-063-007-F01, 10 CFR 54.37(b) TLAA Evaluation Form 3.3.13 NMP-ES-063-GL01, Hatch License Renewal Program Manual 3.3.14 NEI 95-10, Revision 6, Guidelines for Implementing the Requirements of 10 CFR Part 54 - The License Renewal Rule.

Attachment A 10 Program Elements (Excerpted from Appendix A to NUREG-1800)

A.1.2.3 Aging Management Program Elements A.1.2.3.1 Scope of Program The specific program necessary for license renewal should be identified. The scope of the program should include the specific structures and components, the aging of which the program

manages.

A.1.2.3.2 Preventive Actions

1. The activities for prevention and mitigation programs should be described. These actions should mitigate or prevent aging degradation.

2. Some condition or performance monitoring programs do not rely on preventive actions and thus, this information need not be provided.

3. In some cases, condition or performance monitoring programs may also rely on preventive actions. The specific prevention activities should be specified.

A.1.2.3.3 Parameters Monitored or Inspected

1. This program element should identify the aging effects that the program manages and should provide a link between the parameter or parameters that will be monitored and how the monitoring of these parameters will ensure adequate aging management.

2. For a condition monitoring program, the parameter monitored or inspected should be capable of detecting the presence and extent of aging effects. Some examples are measurements of wall thickness and detection and sizing of cracks.

3. For a performance monitoring program, a link should be established between the degradation of the particular structure or component-intended function(s) and the parameter(s) being monitored. An example of linking the degradation of a passive component-intended function with the performance being monitored is linking the fouling of heat exchanger tubes with the heat transfer-intended function. This could be monitored by periodic heat balances. Since this example deals only with one intended function of the tubes (heat transfer), additional programs may be necessary to manage other intended function(s) of the tubes, such as pressure boundary. Thus, a performance monitoring program must ensure that the structure and components are capable of performing their intended functions by using a combination of performance monitoring and evaluation (if outside acceptable limits of acceptance criteria) that demonstrate that a change in performance characteristic is a result of an age-related degradation

mechanism.

4. For prevention or mitigation programs, the parameters monitored should be the specific parameters being controlled to achieve prevention or mitigation of aging effects. An example is the coolant oxygen level that is being controlled in a water chemistry program to mitigate pipe cracking.

A.1.2.3.4 Detection of Aging Effects

1. Detection of aging effects should occur before there is a loss of the structure- and component-intended function(s). The parameters to be monitored or inspected should be appropriate to ensure that the structure- and component-intended function(s) will be adequately maintained for license renewal under all CLB design conditions. Thus, the discussion for the "detection of aging effects" program element should address (a) how the program element would be capable of detecting or identifying the occurrence of age-related degradation or an aging effect prior to a loss of structure and component (SC)-

intended function or (b) for preventive/miti gative programs, how the program would be capable of preventing or mitigating their occurrence prior to a loss of a SC-intended function. The discussion should provide information that links the parameters to be monitored or inspected to the aging effects being managed.

2. Nuclear power plants are licensed based on redundancy, diversity, and defense-in-depth principles. A degraded or failed component reduces the reliability of the system, challenges safety systems, and contributes to plant risk. Thus, the effects of aging on a structure or component should be managed to ensure its availability to perform its intended function(s) as designed when called upon. In this way, all system level-intended function(s), including redundancy, diversity, and defense-in-depth consistent with the plant's CLB, would be maintained for license renewal. A program based solely on detecting structure and component failure should not be considered as an effective AMP for license renewal.

3. This program element describes "when," "where," and "how" program data are collected (i.e., all aspects of activities to collect data as part of the program).

4. For condition monitoring programs, the method or technique (such as visual, volumetric, or surface inspection), frequency, and timing of new, one-time inspections may be linked to plant-specific or industry-wide operating experience. The discussion should provide justification, including codes and standards referenced, that the technique and frequency are adequate to detect the aging effects before a loss of SC-intended function. A program based solely on detecting SC failures is not considered an effective AMP.

For a condition monitoring program, when sampling is used to represent a larger population of SCs, applicants should provide the basis for the inspection population and sample size. The inspection population should be based on such aspects of the SCs as a similarity of materials of construction, fabrication, procurement, design, installation, operating environment, or aging effects. The sample size should be based on such aspects of the SCs as the specific aging effect, location, existing technical information, system and structure design, materials of construction, service environment, or previous failure history. The samples should be biased toward locations most susceptible to the specific aging effect of concern in the period of extended operation. Provisions on expanding the sample size when degradation is detected in the initial sample should also be included.

5. For a performance monitoring program, the "detection of aging effects" program element should discuss and establish the monitoring methods that will be used for performance monitoring. In addition, the "detection of aging effects" program element should also establish and justify the frequency that will be used to implement these performance monitoring activities.

1. For a prevention or mitigation program, the "detection of aging effects" program element should discuss and establish the monitoring methods that the program will use to monitor for the preventive or mitigative parameters that the program controls and should justify the frequency of performing these monitoring activities.

A.1.2.3.5 Monitoring and Trending

1. Monitoring and trending activities should be described, and they should provide a prediction of the extent of degradation and thus effect timely corrective or mitigative actions. Plant-specific and/or industrywideoperating experience may be considered in evaluating the ppropriateness of the technique and frequency.

2. This program element describes "how" the data collected are evaluated and may also include trending for a forward look. This includes an evaluation of the results against the acceptance criteria and a prediction regarding the rate of degradation in order to confirm that timing of the next scheduled inspection will occur before a loss of SC-intended function. Although aging indicators may be quantitative or qualitative, aging indicators should be quantified, to the extent possible, to allow trending. The parameter or indicator trended should be described. The methodology for analyzing the inspection or test results against the acceptance criteria should be described. Trending is a comparison of the current monitoring results with previous monitoring results in order to make predictions for the future.

A.1.2.3.6 Acceptance Criteria

1. The quantitative or qualitative acceptance criteria of the program and its basis should be described. The acceptance criteria, against which the need for corrective actions are evaluated, should ensure that the structure- and component-intended function(s) are maintained consistent with all CLB design conditions during the period of extended operation. The program should include a methodology for analyzing the results against applicable acceptance criteria.

For example, carbon steel pipe wall thinning may occur under certain conditions due to FAC. An AMP for FAC may consist of periodically measuring the pipe wall thickness and comparing that to a specific minimum wall acceptance criterion. Corrective action is taken, such as piping replacement, before deadweight, seismic, and other loads, and this acceptance criterion must be appropriate to ensure that the thinned piping would be able to carry these CLB design loads. This acceptance criterion should provide for timely corrective action before loss of intended function under these CLB design loads.

2. Acceptance criteria could be specific numerical values, or could consist of a discussion of the process for calculating specific numerical values of conditional acceptance criteria to ensure that the structure- and component-intended function(s) will be maintained under all CLB design conditions. Information from available references may be cited.

2. It is not necessary to justify any acceptance criteria taken directly from the design basis information that is included in either the final safety analysis report (FSAR), plant Technical Specifications, or other codes and standards incorporated by reference into NRC regulations; they are a part of the CLB. Nor is it necessary to justify the acceptance criteria that have been established in either NRC-accepted or NRC-endorsed methodology, such as those that may be given in NRC-approved or NRC-endorsed topical reports or NRC-endorsed codes and standards; the acceptance criteria referenced in these types of documents have been subject to an NRC review process and have been approved or endorsed for their application to an NRC-approved or NRC endorsed evaluation methodology. Also, it is not necessary to discuss CLB design loads if the acceptance criteria do not permit degradation because a structure and component without degradation should continue to function as originally designed. Acceptance criteria, which do permit degradation, are based on maintaining the intended function under all CLB design loads.

A.1.2.3.7 Corrective Actions

1. Actions to be taken when the acceptance criteria are not met should be described in appropriate detail or referenced to source documents. Corrective actions, including root cause determination and prevention of recurrence, should be timely.

3. If corrective actions permit analysis without repair or replacement, the analysis should ensure that the structure- and component-intended function(s) are maintained consistent

with the CLB.

4. For safety-related components, an applicant's 10 CFR Part 50, Appendix B, Quality Assurance Program, is an acceptable means to confirm that the corrective actions are done in a manner consistent with the condition monitoring program, preventive program, mitigative program, or performance monitoring program that is credited for aging management. For example, for a plant-specific condition monitoring program that is based on ASME Section XI requirements, the implementation of the Appendix B program should ensure that any corrective actions are performed in accordance with applicable Code requirements or NRC-approved Code cases.

A.1.2.3.8 Confirmation Process

1. The confirmation process should be described. The process ensures that preventive actions are adequate and that appropriate corrective actions have been completed and are effective.

2. The effectiveness of prevention and mitigation programs should be verified periodically. For example, in managing internal corrosion of piping, a mitigation program (water chemistry) may be used to minimize susceptibility to corrosion. However, it also may be necessary to have a condition monitoring program (ultrasonic inspection) to verify that corrosion is indeed insignificant.

3. When corrective actions are necessary, there should be follow-up activities to confirm that the corrective actions have been completed, a root cause determination was performed, and recurrence will be prevented.

A.1.2.3.9 Administrative Controls

1. The administrative controls of the program should be described. Administrative controls provide a formal review and approval process.

2. Any AMPs to be relied on for license renewal should have regulatory and administrative controls. That is the basis for 10 CFR 54.21(d) to require that the FSAR supplement include a summary description of the programs and activities for managing the effects of aging for license renewal. Thus, any informal programs relied on to manage aging for license renewal must be administratively controlled and included in the FSAR

supplement.

A.1.2.3.10 Operating experience

1. Consideration of future plant-specific and industry operating experience relating to aging management programs should be discussed. Reviews of operating experience by the applicant in the future may identify areas where aging management programs should be enhanced or new programs developed. An applicant should commit to a future review of plant-specific and industry operating experience to confirm the effectiveness of its aging management programs or indicate a need to develop new aging management programs. This information should provide objective evidence to support the conclusion that the effects of aging will be managed adequately so that the structure and component intended function(s) will be maintained during the period of extended operation.

2. Operating experience with existing programs should be discussed. The operating experience of AMPs that are existing programs, including past corrective actions resulting in program enhancements or additional programs, should be considered. A past failure would not necessarily invalidate an AMP because the feedback from operating experience should have resulted in appropriate program enhancements or new programs. This information can show where an existing program has succeeded and where it has failed (if at all) in intercepting aging degradation in a timely manner.

This information should provide objective evidence to support the conclusion that the effects of aging will be managed adequately so that the structure- and component-intended function(s) will be maintained during the period of extended operation.

3. For new AMPs that have yet to be implemented at an applicant's facility, the programs have not yet generated any operating experience (OE). However, there may be other relevant plant-specific OE at the plant or generic OE in the industry that is relevant to the AMP's program elements even though the OE was not identified as a result of the implementation of the new program. Thus, for new programs, an applicant may need to consider the impact of relevant OE that results from the past implementation of its existing AMPs that are existing programs and the impact of relevant generic OE on developing the program elements. Therefore, operating experience applicable to new programs should be discussed. Additionally, an applicant should commit to a review of future plant-specific and industry operating experience for new programs to confirm their effectiveness.

NEI 95-10 Revision 6 June 2005 APPENDIX B TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT B-1

NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 10 Structures Compressible Joints and Seals Yes 11 Structures Fuel Pool and Sump Liners Yes 12 Structures Concrete Curbs Yes 13 Structures Offgas Stack and Flue Yes 14 Structures Fire Barriers Yes 15 Structures Pipe Whip Restraints and Jet Impingement Shields Yes 16 Structures Electrical and Instrumentation and Control Penetration Assemblies Yes 17 Structures Instrumentation Racks, Frames, Panels, and

Enclosures Yes 18 Structures Electrical Panels, Racks, Cabinets, and

Other Enclosures Yes B-3 NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 19 Structures Cable Trays and Supports Yes 20 Structures Conduit Yes 21 Structures Tube Track Yes 22 Structures Reactor Vessel Internals Yes 23 Structures ASME Class 1 Hangers and Supports Yes 24 Structures Non-ASME Class 1 Hangers and Supports Yes 25 Structures Snubbers No 26 Reactor Coolant Pressure Boundary Components (Note: the components of the RCPB are defined by each plant's CLB and site specific documentation.

ASME Class 1 Piping Yes B-4 NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 27 Reactor Coolant Pressure Boundary Components Reactor Vessel Yes 28 Reactor Coolant Pressure Boundary Components Reactor Coolant Pumps Yes (Casing) 29 Reactor Coolant Pressure Boundary Components Control Rod Drives No 30 Reactor Coolant Pressure Boundary Components Control Rod Drive Housing Yes 31 Reactor Coolant Pressure Boundary Components Steam Generators Yes 32 Reactor Coolant Pressure Boundary Components Pressurizers Yes 33 Non-Class I Piping Components Underground Piping Yes 34 Non-Class I Piping Components Piping in Low Temperature Demineralized Water Service Yes 35 Non-Class I Piping Components Piping in High Temperature Single Phase

Service Yes B-5

NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 45 Pumps ECCS Pumps Yes (Casing) 46 Pumps Service Water and Fire Pumps Yes (Casing) 47 Pumps Lube Oil and Closed Cooling Water Pumps Yes (Casing) 48 Pumps Condensate Pumps Yes (Casing) 49 Pumps Borated Water Pumps Yes (Casing) 50 Pumps Emergency Service Water Pumps Yes (Casing) 51 Pumps Submersible Pumps Yes (Casing) 52 Turbines Turbine Pump Drives (excluding pumps)

Yes (Casing) 53 Turbines Gas Turbines Yes (Casing)

B-7 NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 54 Turbines Controls (Actuator and Overspeed Trip)

No 55 Engines Fire Pump Diesel Engines No 56 Emergency Diesel Generators Emergency Diesel Generators No 57 Heat Exchangers Condensers Yes 58 Heat Exchangers HVAC Coolers (including housings)

Yes 59 Heat Exchangers Primary Water System Heat Exchangers Yes 60 Heat Exchangers Treated Water System Heat Exchangers Yes 61 Heat Exchangers Closed Cooling Water System Heat Exchangers Yes 62 Heat Exchangers Lubricating Oil System Heat Exchangers Yes B-8 NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 63 Heat Exchangers Raw Water System Heat Exchangers Yes 64 Heat Exchangers Containment Atmospheric System Heat Exchangers Yes 65 Miscellaneous Process Components Gland Seal Blower No 66 Miscellaneous Process Components Recombiners The applicant shall identify the intended function and apply the IPA process to determine if the grouping is active or passive. 67 Miscellaneous Process Components Flexible Connectors Yes 68 Miscellaneous Process Components Strainers Yes 69 Miscellaneous Process Components Rupture Disks Yes 70 Miscellaneous Process Components Steam Traps Yes 71 Miscellaneous Process Components Restricting Orifices Yes B-9

NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 80 Electrical and I&C Communication Equipment (e.g., telephones, video or audio recording or playback equipment, intercoms, computer terminals, electronic messaging, radios, transmission line traps and other power-line carrier equipment)

No 81 Electrical and I&C Electric Heaters, No , Yes for a Pressure Boundary if applicable, See Appendix C Reference 2 82 Electrical and I&C Heat Tracing No See Appendix C Reference 2 83 Electrical and I&C Electrical Controls and Panel Internal Component Assemblies (may include

internal devices such as, but not limited to, switches, breakers, indicating lights, fuse holders, etc.)

(e.g., main control board, HVAC control

board) No 84 Electrical and I&C Elements, RTDs, Sensors, Thermocouples, Transducers (e.g., conductivity elements, flow elements, temperature sensors, radiation sensors,watt

transducers, thermocouples, RTDs, vibration probes, amp transducers, frequency

transducers, power factor transducers, speed

transducers, var. transducers, vibration

transducers, voltage transducers)

No Yes for a Pressure Boundary if applicable

85 Electrical and I&C Fuses No See Appendix C Reference 3 86 Electrical and I&C Generators, Motors (e.g., emergency diesel generators, ECCS and emergency service water pump motors, small

motors, motor-generato r sets, steam turbine generators, combustion turbine generators, fan motors, pump motors, valve motors, air

compressor motors)

No B-11 NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 87 Electrical and I&C High-voltage Insulators (e.g., porcelain switchyard insulators, transmission line insulators)

Yes 88 Electrical and I&C Surge Arresters (e.g., switchyard surge arresters, lightning

arresters, surge suppressers, surge

capacitors, protective capacitors)

No 89 Electrical and I&C Indicators (e.g., differential pr essure indicators, pressure indicators, fl ow indicators, level indicators, speed indicators, temperature

indicators, analog indicators, digital

indicators, LED bar graph indicators, LCD

indicators)

No 90 Electrical and I&C Isolators (e.g., transformer isolators, optical isolators, isolation relays, isolating transfer diodes)

No 91 Electrical and I&C Light Bulbs (e.g., indicating lights, emergency lighting, incandescent light bulbs, fluorescent light

bulbs) No See Appendix C Reference 2 92 Electrical and I&C Loop Controllers (e.g., differential pressure indicating

controllers, flow indi cating controllers, temperature controllers, controllers, speed

controllers, programmabl e logic controller, single loop digital controller, process controllers, manual loader, selector station, hand/auto station, auto/manual station)

No 93 Electrical and I&C Meters (e.g., ammeters, volt meters, frequency

meters, var meters, watt meters, power factor meters, watt-hour meters)

No 94 Electrical and I&C Power Supplies No B-12

NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 103 Electrical and I&C Switchgear, Load Centers, Motor Control Centers, Distribution Panel Internal Component Assemblies (may include

internal devices such as, but not limited to, switches, breakers, indicating lights, etc.)

(e.g., 4.16 kV switchgear, 480V load centers, 480V motor control centers, 250 VDC motor

control centers, 6.9 kV switchgear units, 240/125V power distribution panels)

No 104 Electrical and I&C Transformers (e.g., instrument transformers, load center

transformers, small distribution

transformers, large power transformers, isolation transformers, coupling capacitor

voltage transformers)

No See Appendix C Reference 2 105 Electrical and I&C Transmitters (e.g., differential pressure transmitters, pressure transmitters , flow transmitters, level transmitters, ra diation transmitters, static pressure transmitters)

No 106 Valves Hydraulic Operated Valves Yes (Bodies) 107 Valves Explosive Valves Yes (Bodies) 108 Valves Manual Valves Yes (Bodies) 109 Valves Small Valves Yes (Bodies) 110 Valves Motor-Operated Valves Yes (Bodies)

B-14 NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 111 Valves Air-Operated Valves Yes (Bodies) 112 Valves Main Steam Isolation Valves Yes (Bodies) 113 Valves Small Relief Valves Yes (Bodies) 114 Valves Check Valves Yes (Bodies) 115 Valves Safety Relief Valves Yes (Bodies) 116 Valves Dampers, louvers, and gravity dampers Yes (Housings) 117 Tanks Air Accumulators Yes 118 Tanks Discharge Accumulators (Dampers)

Yes 119 Tanks Boron Acid Storage Tanks Yes B-15 NEI 95-10 Revision 6 June 2005 TYPICAL STRUCTURE, COMPONENT AND COMMODITY GROUPINGS AND ACTIVE/PASSIVE DETERMINATIONS FOR THE INTEGRATED PLANT ASSESSMENT ITEM CATEGORY STRUCTU RE, COMPONENT, OR COMMODITY GROUPING STRUCTURE, COMPONENT, OR COMMODITY GROUPING MEETS 10CFR54.21(a)(1)(i) (YES/NO) 120 Tanks Above Ground Oil Tanks Yes 121 Tanks Underground Oil Tanks Yes 122 Tanks Demineralized Water Tanks Yes 123 Tanks Neutron Shield Tank Yes 124 Fans Ventilation Fans (includes intake fans, exhaust fans, and

purge fans)

Yes (Housings) 125 Fans Other Fans Yes (Housings) 126 Miscellaneous Emergency Lighting No 127 Miscellaneous Hose Stations Yes B-16 1 Davis, James T.

From: Baker, Ray D.

Sent: Friday, April 21, 2000 8:31 AM To: 'William F. Burton (E-mail)'

Subject:

Discussion on Information Presentation in Hatch Application Butch,In response to your e-mail, I am providing the following discussion that should assist in clarifying questions regarding how we presented information in the application. The specific discussion relates to questions you asked regarding the Torus

Submerged Components Inspection Program, A.3.7. The first point of clarification relates to program scope. This program narrowly focuses on components that are submerged in torus water. Thus, it is only applicable to components inside the donut-shaped suppression pool ("torus").

A second point of clarification is to note that the program makes no distinction regarding material. It is applicable to

components having an aging effect requiring management regardless of material, as long as the components are within the torus. One exception to the scope statement will be discussed below. Thus, the way a reader of the application can tell whether a component is submerged in torus water within the torus is by examining the applicable commodity entry line in the appropriate 6-column table in section 3 to see whether the Torus Submerged Components Inspection Program is credited in the Program column. One exception to this "rule" has to do with primary containment miscellaneous steel (p.

3.3-5 of app). Note that A.3.7 is not credited for this item although torus water is listed as one of the environments.

These structural elements receive a separate inspection as a part of IWE/IWL requirements incorporated into our ISI

program. Thus, ISI is credited instead of A.3.7.

In summary, the typical expectation for program coverage of components exposed to torus water can be summarized as follows:- submerged components--carbon steel components typically will credit Protective Coatings and Torus Submerged Components Inspection

--stainless steel components typically will credit Torus Submerged Components Inspection- components exposed to torus water but not submerged in torus

--these components will typically credit the Treated Water Systems Piping Inspections instead The following bulleted items illustrate how the above points are carried through the application:p. 3.2-12heat exchanger shell & tube sheet: these items are not submerged in the torusp. 3.2-13piping: these items are not submerged in the torusp. 3.2-14pump casings: these items are not submerged in the torusp. 3.2-15strainers: the program is applicable regardless of materialp. 3.2-15thermowells & valve bodies: these items are not submerged in the torusp. 3.2-16strainers: the program is applicable regardless of materialp. 3.2-16valve bodies: these items are not submerged in the torusp. 3.2-17piping (C.2.2.3.1): these items are not submerged in the torusp. 3.2-17piping (C.2.2.3.2): the program is applicable regardless of materialp. 3.2-19strainer: the program is applicable regardless of materialp. 3.2-21piping (C.2.2.3.2): the program is applicable regardless of materialp. 3.2-22piping (C.2.2.3.1): these items are not submerged in the torusp. 3.2-23strainer: the program is applicable regardless of materialp. 3.3-4blind flange & CIV: these items are not submerged in the torusp. 3.3-5miscellaneous steel: the submerged items are covered by ISI rather than A.3.7p. 3.3-5piping: these items are not submerged in the torusC.2.2.11.1 & C.2.6.2the items covered by these commodities are not submerged in the torus. Thus, A.3.7 is

not applied to them.SRV piping is found on p. 3.2-6. Note that there is no carbon steel submerged associated with this. The

submerged portion is stainless steel and has A.3.7 creditedVacuum relief piping is found in table 3.2.3-7 associated with T48. Note that carbon steel credits A.3.7 since

some components are submerged.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 261 of 363 Attachment C

Structures and Components Subject to Aging Management Review2.3, Mechanical Systems Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.3-60Component Groups Requiring an Aging Management ReviewTable 2.3.4-16Components Supporting Traveling Water Screens/ Trash Rack System[W33] Intended Functions and Their Component FunctionsMechanical ComponentComponent FunctionsMaterialBoltingPressure BoundaryCarbon SteelSight Glasses*Pressure BoundaryCeramicTrash RacksDebris ProtectionCarbon SteelTraveling ScreenDebris ProtectionCarbon SteelStainless SteelCopper Alloy*Valve BodiesPressure BoundaryCarbon Steel* No aging effects requiring management A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 263 of 363 Attachment C Structures and Components Subject to Aging Management Review2.4, Structures Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.4-6Component Groups Requiring an Aging Management ReviewTable 2.4.3-1Components Supporting Primary Containment [T23] Intended Functions andTheir Component FunctionsStructural ComponentComponent FunctionsMaterialAnchors and BoltsStructural Support;Nonsafety Related Structural SupportCarbon Steel Galvanized SteelStainless SteelBlind Flange*Fission Product BarrierCarbon SteelBolting*Fission Product BarrierCarbon SteelContainment Isolation Valves *Fission Product BarrierCarbon SteelContainment Isolation Valves*Fission Product BarrierStainless SteelContainment Penetrations (Mechanical only)Fission Product BarrierCarbon SteelStainless SteelMiscellaneous SteelStructural Support;Radiation Shielding;Pipe Whip Restraint;Nonsafety Related Structural SupportCarbon SteelGalvanized SteelPiping*Fission Product BarrierCarbon SteelPiping*Fission Product BarrierStainless SteelReinforced ConcreteStructural Support;Shelter/Protection;Flood Barrier;Fission Product Barrier;Radiation Shielding;Missile Barrier; HE/ME ShieldingConcrete Carbon SteelSteel Bellows (inside Vent Pipe)Pressure Boundary;Fission Product BarrierCarbon SteelStainless SteelStructural SteelStructural Support;Shelter/Protection;Radiation Shielding;Missile Barrier;HE/ME Shielding; Pipe Whip Restraint;Nonsafety Related Structural Support;Pressure BoundaryFission Product Barrier;Exchange HeatCarbon SteelStainless SteelTubing*Fission Product Barrier; PressureBoundaryStainless SteelUnreinforced ConcreteRadiation ShieldingUnreinforced Concrete**Vent Pipe, Vent Header,DowncomersFission Product Barrier; Pressure BoundaryCarbon Steel*Piping and valves include components from systems P51, P21, T23, G51, G11, D11, and C51. Theseare all included in function T23-01, Torus/Drywell.**No aging effects requiring management A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 264 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-5Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityBolting / C.2.1.1.6(Class 1)Pressure BoundaryFission Product

BarrierInsideCarbon SteelLoss of PreloadTorque ActivitiesInservice Inspection ProgramBolting / C.2.2.10.1(non-Class 1)Pressure Boundary Fission Product BarrierInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings ProgramCrack Growth Monitor /

C.2.1.1.4(Class 1)Pressure Boundary Fission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection Program Component Cyclic or Transient Limit ProgramTreated Water Systems PipingInspectionsFlow Nozzle / C.2.1.1.3(Class 1)Pressure BoundaryFission Product

BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Inservice Inspection Program Galvanic Susceptibility InspectionsComponent Cyclic or Transient Limit ProgramFlow Accelerated Corrosion ProgramTreated Water Systems Piping InspectionsPiping / C.2.2.1.1(non-Class 1)Pressure Boundary Fission Product

BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems PipingInspectionsFlow Accelerated Corrosion ProgramPiping / C.2.2.1.2(non-Class 1)Pressure Boundary Fission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlTreated Water Systems PipingInspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 265 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-6Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityPiping / C.2.2.2.2(non-Class 1)Pressure BoundaryFission Product

BarrierDemin WaterStainless SteelLoss of MaterialCrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems PipingInspectionsPiping / C.2.2.3.1(non-Class 1)Pressure BoundaryFission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.2.3.2(non-Class 1)Pressure BoundaryFission Product BarrierTorus WaterStainless SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.1.1.3(Class 1)Pressure Boundary Fission Product BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection ProgramGalvanic Susceptibility InspectionsComponent Cyclic or Transient Limit ProgramFlow Accelerated Corrosion ProgramTreated Water Systems PipingInspectionsPiping / C.2.1.1.4(Class 1)Pressure BoundaryFission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection ProgramComponent Cyclic or Transient Limit

Program Treated Water Systems PipingInspectionsPiping / C.2.2.9.1(Class 1)Pressure BoundaryFission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingInservice Inspection ProgramGas Systems Component InspectionsPassive Component InspectionActivities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 266 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-7Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityRestricting Orifice /C.2.1.1.4(Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlComponent Cyclic or Transient Limit ProgramInservice Inspection ProgramTreated Water Systems PipingInspectionsThermowell/

C.2.2.9.1(non-Class 1)Pressure Boundary Fission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingGas Systems Component InspectionsPassive Component InspectionActivitiesThermowell /

C.2.1.1.4 (Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry Control Inservice Inspection Program Component Cyclic or Transient Limit ProgramTreated Water Systems Piping InspectionsValve Bodies / C.2.2.1.1(non-Class 1)Pressure BoundaryFission Product BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Flow Accelerated Corrosion ProgramGalvanic Susceptibility InspectionsTreated Water Systems PipingInspectionsValve Bodies / C.2.2.1.2(non-Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry Control Treated Water Systems Piping InspectionsValve Bodies / C.2.2.9.1 (non-Class 1)Pressure Boundary Fission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingGas Systems Component Inspections Inservice Inspection Program Passive Component Inspection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 267 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-17Table 3.2.3-4 Aging Effects Requiring Management for Components Supporting High Pressure Coolant Injection System [E41] Intende dFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryFission Product BarrierInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Bolting / C.2.2.10.2Pressure Boundary Fission Product BarrierInsideStainless SteelLoss of PreloadTorque ActivitiesFlexible Connector /

C.2.2.9.2Pressure Boundary Fission Product Barrier Dry Wetted GasStainless SteelCrackingLoss of MaterialGas Systems Component InspectionsPiping / C.2.2.1.1Pressure Boundary Fission Product BarrierReactor WaterCarbon SteelLoss of Material CrackingReactor Water Chemistry ControlGalvanic Susceptibility InspectionsFlow Accelerated Corrosion ProgramTreated Water Systems Piping InspectionsPiping / C.2.2.2.1Pressure BoundaryFission Product BarrierDemin WaterCarbon SteelLoss of Material CrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems PipingInspectionsPiping / C.2.2.2.2Pressure Boundary Fission Product BarrierDemin WaterStainless SteelLoss of Material CrackingDemineralized Water and Condensate Storage Tank Chemistry Control Program Treated Water Systems Piping InspectionsPiping / C.2.2.3.1Pressure Boundary Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlGalvanic Susceptibility Inspections Treated Water Systems PipingInspectionsTorus Submerged Components Inspection

Program Protective Coatings ProgramPiping / C.2.2.3.2Pressure Boundary Fission Product BarrierTorus WaterStainless SteelLoss of Material CrackingSuppression Pool Chemistry Control Torus Submerged Components Inspection Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 268 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-25Table 3.2.3-5Aging Effects Requiring Management for Components Supporting Reactor Core Isolation Cooling System [E51] IntendedFunctions and Their Component Functions (Continued)Mechanical Component Component FunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityValve Bodies / C.2.2.9.2Pressure BoundaryFission Product

BarrierWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component Inspections Passive Component Inspection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 269 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-28Table 3.2.3-7Aging Effects Requiring Management for Components Supporting Primary Containment Purge and Inerting System [T48] IntendedFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryInsideCarbon SteelLoss of Preload Loss of MaterialTorque ActivitiesProtective Coatings Program Bolting / C.2.2.10.2Pressure BoundaryInsideStainless SteelLoss of Preload Torque Activities Flex Hose / C.2.2.9.1Pressure BoundaryAirStainless SteelCrackingGas Systems Component InspectionsNitrogen Tank Jacket / C.2.2.9.1Structural SupportAirCarbon SteelCrackingLoss of MaterialGas Systems Component InspectionsPassive Component InspectionActivitiesPiping / C.2.2.3.1Pressure BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlGalvanic Susceptibility InspectionsTorus Submerged ComponentsInspection ProgramProtective Coatings ProgramPiping / C.2.2.3.1Pressure BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.2.3.2Pressure BoundaryTorus WaterStainless SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Treated Water Systems PipingInspectionsPiping / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone RequiredPiping / C.2.2.9.1Pressure BoundaryWetted GasCarbon SteelCrackingLoss of MaterialGas Systems Component Inspections Passive Component InspectionActivitiesPressure Buildup Coil / C.2.2.8.2Pressure BoundaryExchange Heat Dried GasStainless SteelCrackingNone RequiredRupture Disc / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone RequiredStorage Tank / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone Required A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 270 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-33Table 3.2.4-2Aging Effects Requiring Management for Components Supporting Refueling Platform Equipment Assembly [F15] IntendedFunctions and Their Component FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityAnchors and Bolts C.2.6.3Structural support Nonsafety Related Structural SupportInsideCarbon steelLoss of materialProtective Coatings Program Overhead Crane and Refueling PlatformInspectionStructural Monitoring ProgramMiscellaneous Steel C.2.6.3Structural support;Nonsafety RelatedStructural SupportInsideCarbon steelLoss of materialProtective Coatings ProgramOverhead Crane and Refueling Platform Inspection Structural Monitoring ProgramRivetsStructural SupportInsideAluminumNoneNone RequiredStructural Steel

C.2.6.3Structural supportInsideCarbon steelLoss of materialProtective Coatings ProgramOverhead Crane and Refueling Platform InspectionStructural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 271 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-40Table 3.2.4-7Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions a ndTheir Component Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityThermowell /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialCrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramThermowell /

C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialCrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control ProgramValve Bodies /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control ProgramStructural Monitoring ProgramGalvanic Susceptibility InspectionsValve Bodies /C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control Program Structural Monitoring ProgramValve Bodies /

C.2.2.6.3Pressure BoundaryRaw WaterCopper AlloyLoss of MaterialCracking Flow BlockagePSW and RHRSW Chemistry Control

Program Structural Monitoring Program PSW and RHRSW Inspection ProgramVenturi /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Structural Monitoring ProgramGalvanic Susceptibility Inspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 272 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-47Table 3.2.4-13Aging Effects Requiring Management for Components Supporting Reactor Building Crane [T31] Intended Functions and TheirComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityStructural Steel/

C.2.6.3Structural SupportInsideCarbon SteelLoss of MaterialOverhead Crane and Refueling PlatformInspectionProtective Coatings Program Structural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 273 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-50Table 3.2.4-16Aging Effects Requiring Management for Components Supporting Traveling Water Screens / Trash Rack System [W33] IntendedFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityTrash Rack /

C.2.6.3Debris ProtectionSubmergedCarbon SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings Program Traveling Screen /

C.2.6.3Debris ProtectionSubmergedCarbon SteelStainless SteelLoss of MaterialStructural Monitoring ProgramTraveling Screen /

C.2.6.3Debris ProtectionSubmergedCopper AlloyNoneNone RequiredValve Bodies /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramGalvanic Susceptibility InspectionsBolting / C.2.2.10.1Pressure BoundaryOutsideCarbon SteelLoss of MaterialLoss of PreloadTorque Activities Protective Coatings Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 274 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-52Table 3.2.4-18Aging Effects Requiring Management for Components Supporting Fire Protection System [X43] Intended Functions and TheirIntended FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBoltings / C.2.2.10.1Pressure BoundaryInsideOutsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Fire Doors / C.2.3.4.3Fire BarrierInsideCarbon SteelLoss of MaterialFire Protection ActivitiesFire Doors / C.2.3.4.3Fire BarrierInsideGalvanized SteelCopper AlloyStainless Steel AluminumNonmettalic,Inorganic Gypsum

Fibers, NonasbestosSyntheticNonmetallic, OrganicNoneNone RequiredFire Hydrants / C.2.3.1Pressure BoundaryRaw WaterCast IronLoss of MaterialCracking Flow BlockageFire Protection ActivitiesFittings / C.2.3.1Pressure BoundaryRaw Water AirCast IronLoss of MaterialCracking Flow BlockageFire Protection ActivitiesFittings / C.2.3.3Pressure BoundaryAirCopper AlloyCast IronCracking Loss of MaterialFire Protection ActivitiesFusible Material / C.2.3.1Pressure BoundaryInsideNonferrous MetalLoss of MaterialCrackingFire Protection ActivitiesKaowool and Hold-Down Straps / C.2.3.4.3C.2.3.4.2Fire BarrierInsideGalvanized SteelInsulation MaterialCrackingLoss ofMaterialChange in MaterialPropertiesFire Protection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 275 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-4Table 3.3.1-3Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Thei rComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityAnchors and Bolts /

C.2.6.2Structural Support; Nonsafety Related Structural SupportContainment Atmosphere; Embedded; Inside Torus WaterCarbon Steel Galvanized Steel Stainless SteelLoss of MaterialProtective Coatings Program Inservice Inspection ProgramSuppression Pool Chemistry ControlBlind Flange* /C.2.2.3.1Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Treated Water Systems Piping InspectionsContainment IsolationValves* / C.2.2.2.2Fission Product BarrierDemin WaterStainless SteelLoss of MaterialCrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems Piping InspectionsContainment Isolation Valves* / C.2.2.3.1Fission Product BarrierDemin WaterCarbon SteelLoss of MaterialCrackingDemineralized Water and Condensate Storage Tank Chemistry ControlTreated Water Systems Piping InspectionsContainment IsolationValves* / C.2.2.3.1Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialSuppression Pool Chemistry ControlTreated Water Systems Piping InspectionsContainment Isolation Valves* /

C.2.2.6.2C.2.6.2Fission Product BarrierRaw WaterCarbon SteelLoss of MaterialCrackingPassive Component Inspection ActivitiesContainment Isolation Valves* / C.2.2.9.1Fission Product BarrierWetted GasCarbon SteelLoss of MaterialGas Systems Component InspectionsPassive Component Inspection ActivitiesContainment Isolation Valves* / C.2.2.9.2Fission Product BarrierWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component InspectionContainmentPenetrations(Mechanical only) /

C.2.6.2Fission Product BarrierContainmentAtmosphere; Embedded; InsideCarbon SteelStainless SteelLoss of MaterialProtective Coatings ProgramInservice Inspection ProgramPrimary Containment Leakage Rate Testing Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 276 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-6Table 3.3.1-3Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Thei rComponent Functions (Continued)Structural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityStructural Steel /

C.2.6.2Structural Support; Shelter/Protection; Pressure Boundary; Radiation Shielding;Nonsafety RelatedStructural Support; HE/ME Shielding; Missile Barrier;Pipe Whip Restraint;Fission Product

Barrier; Exchange HeatContainment Atmosphere; Inside; Torus Water;EmbeddedCarbon SteelStainless SteelLoss of Material CrackingProtective Coatings Program Primary Containment Leakage RateTesting ProgramInservice Inspection ProgramSuppression Pool Chemistry ControlComponent Cyclic or Transient Limit ProgramTubing* / C.2.2.9.2Fission Product Barrier;Pressure BoundaryWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component InspectionsVent Pipe, VentHeader, Downcomers /

C.2.6.2Pressure BoundaryFission Product BarrierContainment Atmosphere;High Humidity; Inside; Torus WaterCarbon SteelLoss of MaterialCrackingProtective Coatings ProgramInservice Inspection ProgramPrimary Containment Leakage Rate Testing Program Component Cyclic or Transient Limit ProgramSuppression Pool Chemistry ControlBolting / C.2.2.10.1Pressure BoundaryInsideContainment AtmosphereCarbon SteelLoss of MaterialLoss of PreloadProtective Coatings ProgramTorque Activities* Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 277 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-8Table 3.3.1-5Aging Effects Requiring Management for Components Supporting Reactor Building [T29] Intended Functions and TheirComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityAnchors and Bolts /

C.2.6.3Structural Support;Nonsafety RelatedStructural SupportInside; OutsideCarbon SteelLoss of MaterialProtective Coatings Program Structural Monitoring ProgramBlowout Panels /

C.2.6.6Structural Support;Fission Product BarrierInsideAluminum NoneNone RequiredMiscellaneous Steel /

C.2.6.3Structural Support; HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideCarbon SteelGalvanized SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings ProgramMiscellaneous Steel /

C.2.6.3Structural Support; HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideStainless SteelNoneNone RequiredPanel Joint Seals andSealants / C.2.6.7Shelter/Protection;Fission Product BarrierInside; OutsideElastomers;Nonmetallic,InorganicMaterial PropertyChanges andCracking Loss of AdhesionStructural Monitoring ProgramProtective Coatings ProgramReinforced Concrete C.2.6.1Structural Support; Fire Barrier;Shelter/Protection; Flood Barrier;Fission Product Barrier;Radiation Shielding;Missile Barrier;HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideConcreteMasonry Block Carbon SteelLoss of MaterialCrackingStructural Monitoring Program Protective Coatings ProgramStructural SteelC.2.6.3Structural Support; Missile Barrier;Nonsafety RelatedStructural SupportInside; Outside; SubmergedCarbon Steel Galvanized SteelStainless SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings Program Overhead Crane and Refueling PlatformInspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 278 of 363 Attachment C Identification of Commodities C.2 , Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal C.2-60C.2.2.3 Non-Class 1 Components Suppression Pool Water Environment DescriptionComponents within section C.2.2.3 are subject to an environment of suppression pool waterunder normal conditions. The suppression pool water environment is defined in sectionC.1.2.2.C.2.2.3.1Aging Management Review for Non-Class 1 Carbon Steel Components Within theSuppression Pool EnvironmentThis commodity group consists of carbon steel commodities with an internal environment ofsuppression pool water or submerged within the suppression pool. The following component types are included within this evaluation:

• Piping* Valve bodies

• Pump casings

• Thermowells

• Blind flangeSystemsB21 - Nuclear Boiler (2.3.1.2)

• E11 - Residual Heat Removal (2.3.3.2)

• E21 - Core Spray (2.3.3.3)

• E41 - High Pressure Coolant Injection (2.3.3.4)

• E51 - Reactor Core Isolation Cooling (2.3.3.5)

• T23 - Primary Containment (2.4.3)* T48 - Primary Containment Purge and Inerting (2.3.3.7)Aging Effects Requiring Management

• Loss of material (C.1.2.2.1) due to general corrosion, galvanic corrosion, crevicecorrosion, pitting, microbiologically influenced corrosion (MIC), and erosion corrosion.

• Cracking (C.1.2.2.2) due to thermal fatigue.A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links.Aging Management ProgramsAging management programs determined to manage aging effects requiring managementare as follows:

• Suppression Pool Chemistry Control (A.1.7)* Protective Coatings Program (A.2.3)A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 279 of 363 Attachment C

Structures and Components Subject to Aging Management Review2.3, Mechanical Systems Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.3-60Component Groups Requiring an Aging Management ReviewTable 2.3.4-16Components Supporting Traveling Water Screens/ Trash Rack System[W33] Intended Functions and Their Component FunctionsMechanical ComponentComponent FunctionsMaterialBoltingPressure BoundaryCarbon SteelSight Glasses*Pressure BoundaryCeramicTrash RacksDebris ProtectionCarbon SteelTraveling ScreenDebris ProtectionCarbon SteelStainless SteelCopper Alloy*Valve BodiesPressure BoundaryCarbon Steel* No aging effects requiring management A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 281 of 363 Attachment C Structures and Components Subject to Aging Management Review2.3, Mechanical Systems Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.3-66Component Groups Requiring an Aging Management ReviewTable 2.3.4-18Components Supporting Fire Protection System [X43] Intended Functionsand Their Component FunctionsMechanical ComponentComponent FunctionsMaterialBoltingPressure BoundaryCarbon SteelFire DoorsFire BarrierCarbon SteelGalvanized SteelCopper Alloy Stainless SteelAluminumNonmetallic, Inorganic-Gypsum Fibers, nonasbestos synthetic Nonmetallic, organicFire HydrantsPressure BoundaryCast IronFittingsPressure BoundaryCast IronFittingsPressure BoundaryCopper AlloyCast IronFusible MaterialPressure BoundaryNonferrous MetalKaowool and Hold-down StrapsFire BarrierGalvanized Steel, InsulationmaterialNozzlesFlow RestrictionAluminumCopper AlloyNozzlesFlow RestrictionCopper AlloyPenetration SealsFire BarrierConcreteCeramicsCarbon SteelSynthetic Fiber ElastomersPilot ValvesPressure BoundaryAluminumPipe Line StrainersPressure BoundaryCast Iron PipingPressure BoundaryCarbon SteelAluminum Galvanized Steel Copper Alloy Cast Iron PipingPressure BoundaryCarbon SteelStainless Steel PipingPressure BoundaryCarbon SteelGalvanized SteelPump CasingsPressure BoundaryCast IronRestricting OrificesPressure Boundary, FlowRestrictionStainless SteelSprinkler Head BulbsPressure BoundaryCeramics A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 282 of 363 Attachment C Structures and Components Subject to Aging Management Review2.4, Structures Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.4-6Component Groups Requiring an Aging Management ReviewTable 2.4.3-1Components Supporting Primary Containment [T23] Intended Functions andTheir Component FunctionsStructural ComponentComponent FunctionsMaterialAnchors and BoltsStructural Support;Nonsafety Related Structural SupportCarbon Steel Galvanized SteelStainless SteelBlind Flange*Fission Product BarrierCarbon SteelBolting*Fission Product BarrierCarbon SteelContainment Isolation Valves *Fission Product BarrierCarbon SteelContainment Isolation Valves*Fission Product BarrierStainless SteelContainment Penetrations (Mechanical only)Fission Product BarrierCarbon SteelStainless SteelMiscellaneous SteelStructural Support;Radiation Shielding;Pipe Whip Restraint;Nonsafety Related Structural SupportCarbon SteelGalvanized SteelPiping*Fission Product BarrierCarbon SteelPiping*Fission Product BarrierStainless SteelReinforced ConcreteStructural Support;Shelter/Protection;Flood Barrier;Fission Product Barrier;Radiation Shielding;Missile Barrier; HE/ME ShieldingConcrete Carbon SteelSteel Bellows (inside Vent Pipe)Pressure Boundary;Fission Product BarrierCarbon SteelStainless SteelStructural SteelStructural Support;Shelter/Protection;Radiation Shielding;Missile Barrier;HE/ME Shielding; Pipe Whip Restraint;Nonsafety Related Structural Support;Pressure BoundaryFission Product Barrier;Exchange HeatCarbon SteelStainless SteelTubing*Fission Product Barrier; PressureBoundaryStainless SteelUnreinforced ConcreteRadiation ShieldingUnreinforced Concrete**Vent Pipe, Vent Header,DowncomersFission Product Barrier; Pressure BoundaryCarbon Steel*Piping and valves include components from systems P51, P21, T23, G51, G11, D11, and C51. Theseare all included in function T23-01, Torus/Drywell.**No aging effects requiring management A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 283 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-5Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityBolting / C.2.1.1.6(Class 1)Pressure BoundaryFission Product

BarrierInsideCarbon SteelLoss of PreloadTorque ActivitiesInservice Inspection ProgramBolting / C.2.2.10.1(non-Class 1)Pressure Boundary Fission Product BarrierInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings ProgramCrack Growth Monitor /

C.2.1.1.4(Class 1)Pressure Boundary Fission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection Program Component Cyclic or Transient Limit ProgramTreated Water Systems PipingInspectionsFlow Nozzle / C.2.1.1.3(Class 1)Pressure BoundaryFission Product

BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Inservice Inspection Program Galvanic Susceptibility InspectionsComponent Cyclic or Transient Limit ProgramFlow Accelerated Corrosion ProgramTreated Water Systems Piping InspectionsPiping / C.2.2.1.1(non-Class 1)Pressure Boundary Fission Product

BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems PipingInspectionsFlow Accelerated Corrosion ProgramPiping / C.2.2.1.2(non-Class 1)Pressure Boundary Fission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlTreated Water Systems PipingInspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 284 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-6Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityPiping / C.2.2.2.2(non-Class 1)Pressure BoundaryFission Product

BarrierDemin WaterStainless SteelLoss of MaterialCrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems PipingInspectionsPiping / C.2.2.3.1(non-Class 1)Pressure BoundaryFission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.2.3.2(non-Class 1)Pressure BoundaryFission Product BarrierTorus WaterStainless SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.1.1.3(Class 1)Pressure Boundary Fission Product BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection ProgramGalvanic Susceptibility InspectionsComponent Cyclic or Transient Limit ProgramFlow Accelerated Corrosion ProgramTreated Water Systems PipingInspectionsPiping / C.2.1.1.4(Class 1)Pressure BoundaryFission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection ProgramComponent Cyclic or Transient Limit

Program Treated Water Systems PipingInspectionsPiping / C.2.2.9.1(Class 1)Pressure BoundaryFission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingInservice Inspection ProgramGas Systems Component InspectionsPassive Component InspectionActivities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 285 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-7Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityRestricting Orifice /C.2.1.1.4(Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlComponent Cyclic or Transient Limit ProgramInservice Inspection ProgramTreated Water Systems PipingInspectionsThermowell/

C.2.2.9.1(non-Class 1)Pressure Boundary Fission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingGas Systems Component InspectionsPassive Component InspectionActivitiesThermowell /

C.2.1.1.4 (Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry Control Inservice Inspection Program Component Cyclic or Transient Limit ProgramTreated Water Systems Piping InspectionsValve Bodies / C.2.2.1.1(non-Class 1)Pressure BoundaryFission Product BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Flow Accelerated Corrosion ProgramGalvanic Susceptibility InspectionsTreated Water Systems PipingInspectionsValve Bodies / C.2.2.1.2(non-Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry Control Treated Water Systems Piping InspectionsValve Bodies / C.2.2.9.1 (non-Class 1)Pressure Boundary Fission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingGas Systems Component Inspections Inservice Inspection Program Passive Component Inspection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 286 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-17Table 3.2.3-4 Aging Effects Requiring Management for Components Supporting High Pressure Coolant Injection System [E41] Intende dFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryFission Product BarrierInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Bolting / C.2.2.10.2Pressure Boundary Fission Product BarrierInsideStainless SteelLoss of PreloadTorque ActivitiesFlexible Connector /

C.2.2.9.2Pressure Boundary Fission Product Barrier Dry Wetted GasStainless SteelCrackingLoss of MaterialGas Systems Component InspectionsPiping / C.2.2.1.1Pressure Boundary Fission Product BarrierReactor WaterCarbon SteelLoss of Material CrackingReactor Water Chemistry ControlGalvanic Susceptibility InspectionsFlow Accelerated Corrosion ProgramTreated Water Systems Piping InspectionsPiping / C.2.2.2.1Pressure BoundaryFission Product BarrierDemin WaterCarbon SteelLoss of Material CrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems PipingInspectionsPiping / C.2.2.2.2Pressure Boundary Fission Product BarrierDemin WaterStainless SteelLoss of Material CrackingDemineralized Water and Condensate Storage Tank Chemistry Control Program Treated Water Systems Piping InspectionsPiping / C.2.2.3.1Pressure Boundary Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlGalvanic Susceptibility Inspections Treated Water Systems PipingInspectionsTorus Submerged Components Inspection

Program Protective Coatings ProgramPiping / C.2.2.3.2Pressure Boundary Fission Product BarrierTorus WaterStainless SteelLoss of Material CrackingSuppression Pool Chemistry Control Torus Submerged Components Inspection Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 287 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-25Table 3.2.3-5Aging Effects Requiring Management for Components Supporting Reactor Core Isolation Cooling System [E51] IntendedFunctions and Their Component Functions (Continued)Mechanical Component Component FunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityValve Bodies / C.2.2.9.2Pressure BoundaryFission Product

BarrierWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component Inspections Passive Component Inspection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 288 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-28Table 3.2.3-7Aging Effects Requiring Management for Components Supporting Primary Containment Purge and Inerting System [T48] IntendedFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryInsideCarbon SteelLoss of Preload Loss of MaterialTorque ActivitiesProtective Coatings Program Bolting / C.2.2.10.2Pressure BoundaryInsideStainless SteelLoss of Preload Torque Activities Flex Hose / C.2.2.9.1Pressure BoundaryAirStainless SteelCrackingGas Systems Component InspectionsNitrogen Tank Jacket / C.2.2.9.1Structural SupportAirCarbon SteelCrackingLoss of MaterialGas Systems Component InspectionsPassive Component InspectionActivitiesPiping / C.2.2.3.1Pressure BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlGalvanic Susceptibility InspectionsTorus Submerged ComponentsInspection ProgramProtective Coatings ProgramPiping / C.2.2.3.1Pressure BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.2.3.2Pressure BoundaryTorus WaterStainless SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Treated Water Systems PipingInspectionsPiping / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone RequiredPiping / C.2.2.9.1Pressure BoundaryWetted GasCarbon SteelCrackingLoss of MaterialGas Systems Component Inspections Passive Component InspectionActivitiesPressure Buildup Coil / C.2.2.8.2Pressure BoundaryExchange Heat Dried GasStainless SteelCrackingNone RequiredRupture Disc / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone RequiredStorage Tank / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone Required A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 289 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-33Table 3.2.4-2Aging Effects Requiring Management for Components Supporting Refueling Platform Equipment Assembly [F15] IntendedFunctions and Their Component FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityAnchors and Bolts C.2.6.3Structural support Nonsafety Related Structural SupportInsideCarbon steelLoss of materialProtective Coatings Program Overhead Crane and Refueling PlatformInspectionStructural Monitoring ProgramMiscellaneous Steel C.2.6.3Structural support;Nonsafety RelatedStructural SupportInsideCarbon steelLoss of materialProtective Coatings ProgramOverhead Crane and Refueling Platform Inspection Structural Monitoring ProgramRivetsStructural SupportInsideAluminumNoneNone RequiredStructural Steel

C.2.6.3Structural supportInsideCarbon steelLoss of materialProtective Coatings ProgramOverhead Crane and Refueling Platform InspectionStructural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 290 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-40Table 3.2.4-7Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions a ndTheir Component Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityThermowell /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialCrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramThermowell /

C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialCrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control ProgramValve Bodies /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control ProgramStructural Monitoring ProgramGalvanic Susceptibility InspectionsValve Bodies /C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control Program Structural Monitoring ProgramValve Bodies /

C.2.2.6.3Pressure BoundaryRaw WaterCopper AlloyLoss of MaterialCracking Flow BlockagePSW and RHRSW Chemistry Control

Program Structural Monitoring Program PSW and RHRSW Inspection ProgramVenturi /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Structural Monitoring ProgramGalvanic Susceptibility Inspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 291 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-47Table 3.2.4-13Aging Effects Requiring Management for Components Supporting Reactor Building Crane [T31] Intended Functions and TheirComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityStructural Steel/

C.2.6.3Structural SupportInsideCarbon SteelLoss of MaterialOverhead Crane and Refueling PlatformInspectionProtective Coatings Program Structural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 292 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-50Table 3.2.4-16Aging Effects Requiring Management for Components Supporting Traveling Water Screens / Trash Rack System [W33] IntendedFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityTrash Rack /

C.2.6.3Debris ProtectionSubmergedCarbon SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings Program Traveling Screen /

C.2.6.3Debris ProtectionSubmergedCarbon SteelStainless SteelLoss of MaterialStructural Monitoring ProgramTraveling Screen /

C.2.6.3Debris ProtectionSubmergedCopper AlloyNoneNone RequiredValve Bodies /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramGalvanic Susceptibility InspectionsBolting / C.2.2.10.1Pressure BoundaryOutsideCarbon SteelLoss of MaterialLoss of PreloadTorque Activities Protective Coatings Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 293 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-52Table 3.2.4-18Aging Effects Requiring Management for Components Supporting Fire Protection System [X43] Intended Functions and TheirIntended FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBoltings / C.2.2.10.1Pressure BoundaryInsideOutsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Fire Doors / C.2.3.4.3Fire BarrierInsideCarbon SteelLoss of MaterialFire Protection ActivitiesFire Doors / C.2.3.4.3Fire BarrierInsideGalvanized SteelCopper AlloyStainless Steel AluminumNonmettalic,Inorganic Gypsum

Fibers, NonasbestosSyntheticNonmetallic, OrganicNoneNone RequiredFire Hydrants / C.2.3.1Pressure BoundaryRaw WaterCast IronLoss of MaterialCracking Flow BlockageFire Protection ActivitiesFittings / C.2.3.1Pressure BoundaryRaw Water AirCast IronLoss of MaterialCracking Flow BlockageFire Protection ActivitiesFittings / C.2.3.3Pressure BoundaryAirCopper AlloyCast IronCracking Loss of MaterialFire Protection ActivitiesFusible Material / C.2.3.1Pressure BoundaryInsideNonferrous MetalLoss of MaterialCrackingFire Protection ActivitiesKaowool and Hold-Down Straps / C.2.3.4.3C.2.3.4.2Fire BarrierInsideGalvanized SteelInsulation MaterialCrackingLoss ofMaterialChange in MaterialPropertiesFire Protection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 294 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-4Table 3.3.1-3Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Thei rComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityAnchors and Bolts /

C.2.6.2Structural Support; Nonsafety Related Structural SupportContainment Atmosphere; Embedded; Inside Torus WaterCarbon Steel Galvanized Steel Stainless SteelLoss of MaterialProtective Coatings Program Inservice Inspection ProgramSuppression Pool Chemistry ControlBlind Flange* /C.2.2.3.1Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Treated Water Systems Piping InspectionsContainment IsolationValves* / C.2.2.2.2Fission Product BarrierDemin WaterStainless SteelLoss of MaterialCrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems Piping InspectionsContainment Isolation Valves* / C.2.2.3.1Fission Product BarrierDemin WaterCarbon SteelLoss of MaterialCrackingDemineralized Water and Condensate Storage Tank Chemistry ControlTreated Water Systems Piping InspectionsContainment IsolationValves* / C.2.2.3.1Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialSuppression Pool Chemistry ControlTreated Water Systems Piping InspectionsContainment Isolation Valves* /

C.2.2.6.2C.2.6.2Fission Product BarrierRaw WaterCarbon SteelLoss of MaterialCrackingPassive Component Inspection ActivitiesContainment Isolation Valves* / C.2.2.9.1Fission Product BarrierWetted GasCarbon SteelLoss of MaterialGas Systems Component InspectionsPassive Component Inspection ActivitiesContainment Isolation Valves* / C.2.2.9.2Fission Product BarrierWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component InspectionContainmentPenetrations(Mechanical only) /

C.2.6.2Fission Product BarrierContainmentAtmosphere; Embedded; InsideCarbon SteelStainless SteelLoss of MaterialProtective Coatings ProgramInservice Inspection ProgramPrimary Containment Leakage Rate Testing Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 295 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-6Table 3.3.1-3Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Thei rComponent Functions (Continued)Structural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityStructural Steel /

C.2.6.2Structural Support; Shelter/Protection; Pressure Boundary; Radiation Shielding;Nonsafety RelatedStructural Support; HE/ME Shielding; Missile Barrier;Pipe Whip Restraint;Fission Product

Barrier; Exchange HeatContainment Atmosphere; Inside; Torus Water;EmbeddedCarbon SteelStainless SteelLoss of Material CrackingProtective Coatings Program Primary Containment Leakage RateTesting ProgramInservice Inspection ProgramSuppression Pool Chemistry ControlComponent Cyclic or Transient Limit ProgramTubing* / C.2.2.9.2Fission Product Barrier;Pressure BoundaryWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component InspectionsVent Pipe, VentHeader, Downcomers /

C.2.6.2Pressure BoundaryFission Product BarrierContainment Atmosphere;High Humidity; Inside; Torus WaterCarbon SteelLoss of MaterialCrackingProtective Coatings ProgramInservice Inspection ProgramPrimary Containment Leakage Rate Testing Program Component Cyclic or Transient Limit ProgramSuppression Pool Chemistry ControlBolting / C.2.2.10.1Pressure BoundaryInsideContainment AtmosphereCarbon SteelLoss of MaterialLoss of PreloadProtective Coatings ProgramTorque Activities* Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 296 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-8Table 3.3.1-5Aging Effects Requiring Management for Components Supporting Reactor Building [T29] Intended Functions and TheirComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityAnchors and Bolts /

C.2.6.3Structural Support;Nonsafety RelatedStructural SupportInside; OutsideCarbon SteelLoss of MaterialProtective Coatings Program Structural Monitoring ProgramBlowout Panels /

C.2.6.6Structural Support;Fission Product BarrierInsideAluminum NoneNone RequiredMiscellaneous Steel /

C.2.6.3Structural Support; HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideCarbon SteelGalvanized SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings ProgramMiscellaneous Steel /

C.2.6.3Structural Support; HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideStainless SteelNoneNone RequiredPanel Joint Seals andSealants / C.2.6.7Shelter/Protection;Fission Product BarrierInside; OutsideElastomers;Nonmetallic,InorganicMaterial PropertyChanges andCracking Loss of AdhesionStructural Monitoring ProgramProtective Coatings ProgramReinforced Concrete C.2.6.1Structural Support; Fire Barrier;Shelter/Protection; Flood Barrier;Fission Product Barrier;Radiation Shielding;Missile Barrier;HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideConcreteMasonry Block Carbon SteelLoss of MaterialCrackingStructural Monitoring Program Protective Coatings ProgramStructural SteelC.2.6.3Structural Support; Missile Barrier;Nonsafety RelatedStructural SupportInside; Outside; SubmergedCarbon Steel Galvanized SteelStainless SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings Program Overhead Crane and Refueling PlatformInspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 297 of 363 Attachment C Identification of Commodities C.2 , Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal C.2-60C.2.2.3 Non-Class 1 Components Suppression Pool Water Environment DescriptionComponents within section C.2.2.3 are subject to an environment of suppression pool waterunder normal conditions. The suppression pool water environment is defined in sectionC.1.2.2.C.2.2.3.1Aging Management Review for Non-Class 1 Carbon Steel Components Within theSuppression Pool EnvironmentThis commodity group consists of carbon steel commodities with an internal environment ofsuppression pool water or submerged within the suppression pool. The following component types are included within this evaluation:

• Piping* Valve bodies

• Pump casings

• Thermowells

• Blind flangeSystemsB21 - Nuclear Boiler (2.3.1.2)

• E11 - Residual Heat Removal (2.3.3.2)

• E21 - Core Spray (2.3.3.3)

• E41 - High Pressure Coolant Injection (2.3.3.4)

• E51 - Reactor Core Isolation Cooling (2.3.3.5)

• T23 - Primary Containment (2.4.3)* T48 - Primary Containment Purge and Inerting (2.3.3.7)Aging Effects Requiring Management

• Loss of material (C.1.2.2.1) due to general corrosion, galvanic corrosion, crevicecorrosion, pitting, microbiologically influenced corrosion (MIC), and erosion corrosion.

• Cracking (C.1.2.2.2) due to thermal fatigue.A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links.Aging Management ProgramsAging management programs determined to manage aging effects requiring managementare as follows:

• Suppression Pool Chemistry Control (A.1.7)* Protective Coatings Program (A.2.3)A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 298 of 363 Attachment C

Structures and Components Subject to Aging Management Review2.3, Mechanical Systems Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.3-60Component Groups Requiring an Aging Management ReviewTable 2.3.4-16Components Supporting Traveling Water Screens/ Trash Rack System[W33] Intended Functions and Their Component FunctionsMechanical ComponentComponent FunctionsMaterialBoltingPressure BoundaryCarbon SteelSight Glasses*Pressure BoundaryCeramicTrash RacksDebris ProtectionCarbon SteelTraveling ScreenDebris ProtectionCarbon SteelStainless SteelCopper Alloy*Valve BodiesPressure BoundaryCarbon Steel* No aging effects requiring management A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 300 of 363 Attachment C Structures and Components Subject to Aging Management Review2.3, Mechanical Systems Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.3-66Component Groups Requiring an Aging Management ReviewTable 2.3.4-18Components Supporting Fire Protection System [X43] Intended Functionsand Their Component FunctionsMechanical ComponentComponent FunctionsMaterialBoltingPressure BoundaryCarbon SteelFire DoorsFire BarrierCarbon SteelGalvanized SteelCopper Alloy Stainless SteelAluminumNonmetallic, Inorganic-Gypsum Fibers, nonasbestos synthetic Nonmetallic, organicFire HydrantsPressure BoundaryCast IronFittingsPressure BoundaryCast IronFittingsPressure BoundaryCopper AlloyCast IronFusible MaterialPressure BoundaryNonferrous MetalKaowool and Hold-down StrapsFire BarrierGalvanized Steel, InsulationmaterialNozzlesFlow RestrictionAluminumCopper AlloyNozzlesFlow RestrictionCopper AlloyPenetration SealsFire BarrierConcreteCeramicsCarbon SteelSynthetic Fiber ElastomersPilot ValvesPressure BoundaryAluminumPipe Line StrainersPressure BoundaryCast Iron PipingPressure BoundaryCarbon SteelAluminum Galvanized Steel Copper Alloy Cast Iron PipingPressure BoundaryCarbon SteelStainless Steel PipingPressure BoundaryCarbon SteelGalvanized SteelPump CasingsPressure BoundaryCast IronRestricting OrificesPressure Boundary, FlowRestrictionStainless SteelSprinkler Head BulbsPressure BoundaryCeramics A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 301 of 363 Attachment C Structures and Components Subject to Aging Management Review2.4, Structures Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.4-6Component Groups Requiring an Aging Management ReviewTable 2.4.3-1Components Supporting Primary Containment [T23] Intended Functions andTheir Component FunctionsStructural ComponentComponent FunctionsMaterialAnchors and BoltsStructural Support;Nonsafety Related Structural SupportCarbon Steel Galvanized SteelStainless SteelBlind Flange*Fission Product BarrierCarbon SteelBolting*Fission Product BarrierCarbon SteelContainment Isolation Valves *Fission Product BarrierCarbon SteelContainment Isolation Valves*Fission Product BarrierStainless SteelContainment Penetrations (Mechanical only)Fission Product BarrierCarbon SteelStainless SteelMiscellaneous SteelStructural Support;Radiation Shielding;Pipe Whip Restraint;Nonsafety Related Structural SupportCarbon SteelGalvanized SteelPiping*Fission Product BarrierCarbon SteelPiping*Fission Product BarrierStainless SteelReinforced ConcreteStructural Support;Shelter/Protection;Flood Barrier;Fission Product Barrier;Radiation Shielding;Missile Barrier; HE/ME ShieldingConcrete Carbon SteelSteel Bellows (inside Vent Pipe)Pressure Boundary;Fission Product BarrierCarbon SteelStainless SteelStructural SteelStructural Support;Shelter/Protection;Radiation Shielding;Missile Barrier;HE/ME Shielding; Pipe Whip Restraint;Nonsafety Related Structural Support;Pressure BoundaryFission Product Barrier;Exchange HeatCarbon SteelStainless SteelTubing*Fission Product Barrier; PressureBoundaryStainless SteelUnreinforced ConcreteRadiation ShieldingUnreinforced Concrete**Vent Pipe, Vent Header,DowncomersFission Product Barrier; Pressure BoundaryCarbon Steel*Piping and valves include components from systems P51, P21, T23, G51, G11, D11, and C51. Theseare all included in function T23-01, Torus/Drywell.**No aging effects requiring management A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 302 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-5Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityBolting / C.2.1.1.6(Class 1)Pressure BoundaryFission Product

BarrierInsideCarbon SteelLoss of PreloadTorque ActivitiesInservice Inspection ProgramBolting / C.2.2.10.1(non-Class 1)Pressure Boundary Fission Product BarrierInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings ProgramCrack Growth Monitor /

C.2.1.1.4(Class 1)Pressure Boundary Fission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection Program Component Cyclic or Transient Limit ProgramTreated Water Systems PipingInspectionsFlow Nozzle / C.2.1.1.3(Class 1)Pressure BoundaryFission Product

BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Inservice Inspection Program Galvanic Susceptibility InspectionsComponent Cyclic or Transient Limit ProgramFlow Accelerated Corrosion ProgramTreated Water Systems Piping InspectionsPiping / C.2.2.1.1(non-Class 1)Pressure Boundary Fission Product

BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems PipingInspectionsFlow Accelerated Corrosion ProgramPiping / C.2.2.1.2(non-Class 1)Pressure Boundary Fission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlTreated Water Systems PipingInspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 303 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-6Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityPiping / C.2.2.2.2(non-Class 1)Pressure BoundaryFission Product

BarrierDemin WaterStainless SteelLoss of MaterialCrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems PipingInspectionsPiping / C.2.2.3.1(non-Class 1)Pressure BoundaryFission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.2.3.2(non-Class 1)Pressure BoundaryFission Product BarrierTorus WaterStainless SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.1.1.3(Class 1)Pressure Boundary Fission Product BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection ProgramGalvanic Susceptibility InspectionsComponent Cyclic or Transient Limit ProgramFlow Accelerated Corrosion ProgramTreated Water Systems PipingInspectionsPiping / C.2.1.1.4(Class 1)Pressure BoundaryFission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection ProgramComponent Cyclic or Transient Limit

Program Treated Water Systems PipingInspectionsPiping / C.2.2.9.1 (non-Class 1)Pressure BoundaryFission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingInservice Inspection ProgramGas Systems Component InspectionsPassive Component InspectionActivities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 304 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-7Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityRestricting Orifice /C.2.1.1.4(Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlComponent Cyclic or Transient Limit ProgramInservice Inspection ProgramTreated Water Systems PipingInspectionsThermowell/

C.2.2.9.1(non-Class 1)Pressure Boundary Fission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingGas Systems Component InspectionsPassive Component InspectionActivitiesThermowell /

C.2.1.1.4 (Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry Control Inservice Inspection Program Component Cyclic or Transient Limit ProgramTreated Water Systems Piping InspectionsValve Bodies / C.2.2.1.1(non-Class 1)Pressure BoundaryFission Product BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Flow Accelerated Corrosion ProgramGalvanic Susceptibility InspectionsTreated Water Systems PipingInspectionsValve Bodies / C.2.2.1.2(non-Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry Control Treated Water Systems Piping InspectionsValve Bodies / C.2.2.9.1 (non-Class 1)Pressure Boundary Fission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingGas Systems Component Inspections Inservice Inspection Program Passive Component Inspection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 305 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-17Table 3.2.3-4 Aging Effects Requiring Management for Components Supporting High Pressure Coolant Injection System [E41] Intende dFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryFission Product BarrierInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Bolting / C.2.2.10.2Pressure Boundary Fission Product BarrierInsideStainless SteelLoss of PreloadTorque ActivitiesFlexible Connector /

C.2.2.9.2Pressure Boundary Fission Product Barrier Dry Wetted GasStainless SteelCrackingLoss of MaterialGas Systems Component InspectionsPiping / C.2.2.1.1Pressure Boundary Fission Product BarrierReactor WaterCarbon SteelLoss of Material CrackingReactor Water Chemistry ControlGalvanic Susceptibility InspectionsFlow Accelerated Corrosion ProgramTreated Water Systems Piping InspectionsPiping / C.2.2.2.1Pressure BoundaryFission Product BarrierDemin WaterCarbon SteelLoss of Material CrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems PipingInspectionsPiping / C.2.2.2.2Pressure Boundary Fission Product BarrierDemin WaterStainless SteelLoss of Material CrackingDemineralized Water and Condensate Storage Tank Chemistry Control Program Treated Water Systems Piping InspectionsPiping / C.2.2.3.1Pressure Boundary Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlGalvanic Susceptibility Inspections Treated Water Systems PipingInspectionsTorus Submerged Components Inspection

Program Protective Coatings ProgramPiping / C.2.2.3.2Pressure Boundary Fission Product BarrierTorus WaterStainless SteelLoss of Material CrackingSuppression Pool Chemistry Control Torus Submerged Components Inspection Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 306 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-25Table 3.2.3-5Aging Effects Requiring Management for Components Supporting Reactor Core Isolation Cooling System [E51] IntendedFunctions and Their Component Functions (Continued)Mechanical Component Component FunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityValve Bodies / C.2.2.9.2Pressure BoundaryFission Product

BarrierWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component Inspections Passive Component Inspection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 307 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-28Table 3.2.3-7Aging Effects Requiring Management for Components Supporting Primary Containment Purge and Inerting System [T48] IntendedFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryInsideCarbon SteelLoss of Preload Loss of MaterialTorque ActivitiesProtective Coatings Program Bolting / C.2.2.10.2Pressure BoundaryInsideStainless SteelLoss of Preload Torque Activities Flex Hose / C.2.2.9.1Pressure BoundaryAirStainless SteelCrackingGas Systems Component InspectionsNitrogen Tank Jacket / C.2.2.9.1Structural SupportAirCarbon SteelCrackingLoss of MaterialGas Systems Component InspectionsPassive Component InspectionActivitiesPiping / C.2.2.3.1Pressure BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlGalvanic Susceptibility InspectionsTorus Submerged ComponentsInspection ProgramProtective Coatings ProgramPiping / C.2.2.3.1Pressure BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.2.3.2Pressure BoundaryTorus WaterStainless SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Treated Water Systems PipingInspectionsPiping / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone RequiredPiping / C.2.2.9.1Pressure BoundaryWetted GasCarbon SteelCrackingLoss of MaterialGas Systems Component Inspections Passive Component InspectionActivitiesPressure Buildup Coil / C.2.2.8.2Pressure BoundaryExchange Heat Dried GasStainless SteelCrackingNone RequiredRupture Disc / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone RequiredStorage Tank / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone Required A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 308 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-33Table 3.2.4-2Aging Effects Requiring Management for Components Supporting Refueling Platform Equipment Assembly [F15] IntendedFunctions and Their Component FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityAnchors and Bolts C.2.6.3Structural support Nonsafety Related Structural SupportInsideCarbon steelLoss of materialProtective Coatings Program Overhead Crane and Refueling PlatformInspectionStructural Monitoring ProgramMiscellaneous Steel C.2.6.3Structural support;Nonsafety RelatedStructural SupportInsideCarbon steelLoss of materialProtective Coatings ProgramOverhead Crane and Refueling Platform Inspection Structural Monitoring ProgramRivetsStructural SupportInsideAluminumNoneNone RequiredStructural Steel

C.2.6.3Structural supportInsideCarbon steelLoss of materialProtective Coatings ProgramOverhead Crane and Refueling Platform InspectionStructural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 309 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-40Table 3.2.4-7Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions a ndTheir Component Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityThermowell /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialCrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramThermowell /

C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialCrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control ProgramValve Bodies /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control ProgramStructural Monitoring ProgramGalvanic Susceptibility InspectionsValve Bodies /C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control Program Structural Monitoring ProgramValve Bodies /

C.2.2.6.3Pressure BoundaryRaw WaterCopper AlloyLoss of MaterialCracking Flow BlockagePSW and RHRSW Chemistry Control

Program Structural Monitoring Program PSW and RHRSW Inspection ProgramVenturi /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Structural Monitoring ProgramGalvanic Susceptibility Inspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 310 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-47Table 3.2.4-13Aging Effects Requiring Management for Components Supporting Reactor Building Crane [T31] Intended Functions and TheirComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityStructural Steel/

C.2.6.3Structural SupportInsideCarbon SteelLoss of MaterialOverhead Crane and Refueling PlatformInspectionProtective Coatings Program Structural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 311 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-50Table 3.2.4-16Aging Effects Requiring Management for Components Supporting Traveling Water Screens / Trash Rack System [W33] IntendedFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityTrash Rack /

C.2.6.3Debris ProtectionSubmergedCarbon SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings Program Traveling Screen /

C.2.6.3Debris ProtectionSubmergedCarbon SteelStainless SteelLoss of MaterialStructural Monitoring ProgramTraveling Screen /

C.2.6.3Debris ProtectionSubmergedCopper AlloyNoneNone RequiredValve Bodies /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramGalvanic Susceptibility InspectionsBolting / C.2.2.10.1Pressure BoundaryOutsideCarbon SteelLoss of MaterialLoss of PreloadTorque Activities Protective Coatings Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 312 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-52Table 3.2.4-18Aging Effects Requiring Management for Components Supporting Fire Protection System [X43] Intended Functions and TheirIntended FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBoltings / C.2.2.10.1Pressure BoundaryInsideOutsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Fire Doors / C.2.3.4.3Fire BarrierInsideCarbon SteelLoss of MaterialFire Protection ActivitiesFire Doors / C.2.3.4.3Fire BarrierInsideGalvanized SteelCopper AlloyStainless Steel AluminumNonmettalic,Inorganic Gypsum

Fibers, NonasbestosSyntheticNonmetallic, OrganicNoneNone RequiredFire Hydrants / C.2.3.1Pressure BoundaryRaw WaterCast IronLoss of MaterialCracking Flow BlockageFire Protection ActivitiesFittings / C.2.3.1Pressure BoundaryRaw Water AirCast IronLoss of MaterialCracking Flow BlockageFire Protection ActivitiesFittings / C.2.3.3Pressure BoundaryAirCopper AlloyCast IronCracking Loss of MaterialFire Protection ActivitiesFusible Material / C.2.3.1Pressure BoundaryInsideNonferrous MetalLoss of MaterialCrackingFire Protection ActivitiesKaowool and Hold-Down Straps / C.2.3.4.3C.2.3.4.2Fire BarrierInsideGalvanized SteelInsulation MaterialCrackingLoss ofMaterialChange in MaterialPropertiesFire Protection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 313 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-4Table 3.3.1-3Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Thei rComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityAnchors and Bolts /

C.2.6.2Structural Support; Nonsafety Related Structural SupportContainment Atmosphere; Embedded; Inside Torus WaterCarbon Steel Galvanized Steel Stainless SteelLoss of MaterialProtective Coatings Program Inservice Inspection ProgramSuppression Pool Chemistry ControlBlind Flange* /C.2.2.3.1Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Treated Water Systems Piping InspectionsContainment IsolationValves* / C.2.2.2.2Fission Product BarrierDemin WaterStainless SteelLoss of MaterialCrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems Piping InspectionsContainment Isolation Valves* / C.2.2.3.1Fission Product BarrierDemin WaterCarbon SteelLoss of MaterialCrackingDemineralized Water and Condensate Storage Tank Chemistry ControlTreated Water Systems Piping InspectionsContainment IsolationValves* / C.2.2.3.1Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialSuppression Pool Chemistry ControlTreated Water Systems Piping InspectionsContainment Isolation Valves* /

C.2.2.6.2C.2.6.2Fission Product BarrierRaw WaterCarbon SteelLoss of MaterialCrackingPassive Component Inspection ActivitiesContainment Isolation Valves* / C.2.2.9.1Fission Product BarrierWetted GasCarbon SteelLoss of MaterialGas Systems Component InspectionsPassive Component Inspection ActivitiesContainment Isolation Valves* / C.2.2.9.2Fission Product BarrierWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component InspectionContainmentPenetrations(Mechanical only) /

C.2.6.2Fission Product BarrierContainmentAtmosphere; Embedded; InsideCarbon SteelStainless SteelLoss of MaterialProtective Coatings ProgramInservice Inspection ProgramPrimary Containment Leakage Rate Testing Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 314 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-6Table 3.3.1-3Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Thei rComponent Functions (Continued)Structural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityStructural Steel /

C.2.6.2Structural Support; Shelter/Protection; Pressure Boundary; Radiation Shielding;Nonsafety RelatedStructural Support; HE/ME Shielding; Missile Barrier;Pipe Whip Restraint;Fission Product

Barrier; Exchange HeatContainment Atmosphere; Inside; Torus Water;EmbeddedCarbon SteelStainless SteelLoss of Material CrackingProtective Coatings Program Primary Containment Leakage RateTesting ProgramInservice Inspection ProgramSuppression Pool Chemistry ControlComponent Cyclic or Transient Limit ProgramTubing* / C.2.2.9.2Fission Product Barrier;Pressure BoundaryWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component InspectionsVent Pipe, VentHeader, Downcomers /

C.2.6.2Pressure BoundaryFission Product BarrierContainment Atmosphere;High Humidity; Inside; Torus WaterCarbon SteelLoss of MaterialCrackingProtective Coatings ProgramInservice Inspection ProgramPrimary Containment Leakage Rate Testing Program Component Cyclic or Transient Limit ProgramSuppression Pool Chemistry ControlBolting / C.2.2.10.1Pressure BoundaryInsideContainment AtmosphereCarbon SteelLoss of MaterialLoss of PreloadProtective Coatings ProgramTorque Activities* Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 315 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-8Table 3.3.1-5Aging Effects Requiring Management for Components Supporting Reactor Building [T29] Intended Functions and TheirComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityAnchors and Bolts /

C.2.6.3Structural Support;Nonsafety RelatedStructural SupportInside; OutsideCarbon SteelLoss of MaterialProtective Coatings Program Structural Monitoring ProgramBlowout Panels /

C.2.6.6Structural Support;Fission Product BarrierInsideAluminum NoneNone RequiredMiscellaneous Steel /

C.2.6.3Structural Support; HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideCarbon SteelGalvanized SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings ProgramMiscellaneous Steel /

C.2.6.3Structural Support; HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideStainless SteelNoneNone RequiredPanel Joint Seals andSealants / C.2.6.7Shelter/Protection;Fission Product BarrierInside; OutsideElastomers;Nonmetallic,InorganicMaterial PropertyChanges andCracking Loss of AdhesionStructural Monitoring ProgramProtective Coatings ProgramReinforced Concrete C.2.6.1Structural Support; Fire Barrier;Shelter/Protection; Flood Barrier;Fission Product Barrier;Radiation Shielding;Missile Barrier;HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideConcreteMasonry Block Carbon SteelLoss of MaterialCrackingStructural Monitoring Program Protective Coatings ProgramStructural SteelC.2.6.3Structural Support; Missile Barrier;Nonsafety RelatedStructural SupportInside; Outside; SubmergedCarbon Steel Galvanized SteelStainless SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings Program Overhead Crane and Refueling PlatformInspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 316 of 363 Attachment C Identification of Commodities C.2 , Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal C.2-60C.2.2.3 Non-Class 1 Components Suppression Pool Water Environment DescriptionComponents within section C.2.2.3 are subject to an environment of suppression pool waterunder normal conditions. The suppression pool water environment is defined in sectionC.1.2.2.C.2.2.3.1Aging Management Review for Non-Class 1 Carbon Steel Components Within theSuppression Pool EnvironmentThis commodity group consists of carbon steel commodities with an internal environment ofsuppression pool water or submerged within the suppression pool. The following component types are included within this evaluation:

• Piping* Valve bodies

• Pump casings

• Thermowells

• Blind flangeSystemsB21 - Nuclear Boiler (2.3.1.2)

• E11 - Residual Heat Removal (2.3.3.2)

• E21 - Core Spray (2.3.3.3)

• E41 - High Pressure Coolant Injection (2.3.3.4)

• E51 - Reactor Core Isolation Cooling (2.3.3.5)

• T23 - Primary Containment (2.4.3)* T48 - Primary Containment Purge and Inerting (2.3.3.7)Aging Effects Requiring Management

• Loss of material (C.1.2.2.1) due to general corrosion, galvanic corrosion, crevicecorrosion, pitting, microbiologically influenced corrosion (MIC), and erosion corrosion.

• Cracking (C.1.2.2.2) due to thermal fatigue.A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links.Aging Management ProgramsAging management programs determined to manage aging effects requiring managementare as follows:

• Suppression Pool Chemistry Control (A.1.7)* Protective Coatings Program (A.2.3)A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 317 of 363 Attachment C

Introduction1.1, General Information - 10 CFR 54.19Edwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal1.1-6Patrick Bowie,Board MemberP. O. Box 430 LaGrange, Georgia 30241The Honorable Ansley L. Meaders, Board Member205 Lawrence Street Marietta, Georgia 30061Roland C. Stubbs Jr.,

Board Member113 Sylvan Terrace Sylvania, Georgia 30467The Honorable Gerald Thompson Board MemberP. O. Box 425 Fitzgerald, Georgia 31750Kerry Waldron, Board MemberP. O. Box 672 Thomaston, Georgia 30286-0009Joel T. Wood Board MemberP. O. Box 487 West Point, Georgia 31833Principal OfficersRobert P. Johnston,President14370 Riveredge Pkwy. NW Atlanta, Georgia 30328Mary Jackson,Vice President and Chief Financial Officer14370 Riveredge Pkwy. NW Atlanta, Georgia 30328James Fuller, Treasurer14370 Riveredge Pkwy. NW Atlanta, Georgia 30328MEAG is neither owned, controlled, nor dominated by an alien, foreign corporation, or foreign government.OGLETHORPE POWER CORPORATIONOglethorpe Power Corporation (an Electric Membership Corporation) operating on a not-for-profit basis, was organized under the Georgia Electric Membership Corporation Act (OfficialCode of Georgia Annotated, Title 46, Chapter 3, Article 4) and other applicable laws of theState of Georgia.The names and addresses of Oglethorpes principal officers and the members of itsgoverning body, all of whom are citizens of the United States, are as follows:Board of DirectorsJ. Calvin Earwood,Chairman2100 East Exchange Place Tucker, GA 30085-1349 A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 319 of 363 Attachment C Introduction1.1, General Information - 10 CFR 54.19Edwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal1.1-7Benny W. DenhamSam Rabun ,Vice ChairmanCentral Regional Director2100 East Exchange PlaceTucker, GA 30085-1349Mac F. Oglesby, Treasurer2100 East Exchange Place Tucker, GA 30085-1349Larry N. Chadwick, NW Regional Director2100 East Exchange Place Tucker, GA 30085-1349Sammy Jenkins,SE Regional Director2100 East Exchange Place Tucker, GA 30085-1349Sam RabunBenny W. Denham

,Central SW Regional Director2100 East Exchange PlaceTucker, GA 30085-1349Ashley C. Brown, Outside Director2100 East Exchange Place Tucker, GA 30085-1349Newton A. Campbell,Outside Director2100 East Exchange PlaceTucker, GA 30085-1349Wm. Ronald Duffy, Outside Director2100 East Exchange Place Tucker, GA 30085-1349John S. Ranson, Outside DirectorJeffrey D. TranenOutside Director2100 East Exchange Place Tucker, GA 30085-13492100 East Exchange PlaceTucker, GA 30085-1349Principal OfficersThomas A. Smith,President and Chief Executive Officer2100 East Exchange Place Tucker, GA 30085-1349Michael W. Price,Chief Operating Officer2100 East Exchange Place Tucker, GA 30085-1349W. Clayton Robbins,Senior Vice President, Finance and Administration2100 East Exchange Place Tucker, GA 30085-1349Clarence D. Mitchell, Senior Vice President,Operations and Projects2100 East Exchange PlaceTucker, GA 30085-1349Betsy Higgins, Vice President, Assistant to the CEO2100 East Exchange Place Tucker, GA 30085-1349 A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 320 of 363 Attachment C Introduction1.1, General Information - 10 CFR 54.19Edwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal1.1-8Dale R. Murphy,Vice President,Planning and Administration2100 East Exchange PlaceTucker, GA 30085-1349Robert D. Steele, Vice President, External Affairs2100 East Exchange Place Tucker, GA 30085-1349Glenn Loomer Vice President,Contract s Administration and Analysis2100 East Exchange PlaceTucker, GA 30085-1349Willie Collins, Controller and Chief Risk Officer2100 East Exchange Place Tucker, GA 30085-1349James E. Kofron, Corporate Treasurer2100 East Exchange Place Tucker, GA 30085-1349Patricia N. Nash,Corporate Secretary2100 East Exchange Place Tucker, GA 30085-1349Oglethorpe is neither owned, controlled, nor dominated by an alien, foreign corporation, orforeign government.CITY OF DALTONThe names and addresses of Daltons governing body (councilmen) and principal officers(mayor and city administrator), all of whom are citizens of the United States, are as follows:

CouncilmenRay Elrod,Mayor1508 Rio Vista Drive Dalton, GA 30720Bobby Joe GrantParamount PrintingP. O. Box 4569 Dalton, GA 30719-4569Charles Whitener123 Lisa LaneDalton, GA 30720Terry Christie607 Murray Hill DriveDalton, GA 30720Michael Robinson2006 West Brookhaven CircleDalton, GA 30720 A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 321 of 363 Attachment C Introduction1.1, General Information - 10 CFR 54.19Edwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal1.1-9OfficersRay Elrod,Mayor1508 Rio Vista Drive Dalton, GA 30720Butch Sanders,City AdministratorCity Hall P. O. Box 1205 Dalton, GA 30722-1205Faye Martin, City ClerkCity Hall P. O. Box 1205 Dalton, GA 30722-1205Dalton is neither owned, controlled, nor dominated by an alien, foreign corporation, or foreign government.The names and addresses of Dalton Utilities governing body (Commissioners) and principalofficers (chairman, president/chief executive officer, and secretary), all of whom are citizens of the United States, are as follows:CommissionersJustin RobinsonChairman2203 Druid Lane Dalton, GA 30720Norman D. BurkettVice Chairman2209 Rocky Face Circle Dalton, GA 30720Todd ReigelSecretaryc/o Paradigm Printing, Inc.

429 Virgil Drive Dalton, GA 30720George Mitchellc/o Dalton Paving & Construction Company 530 North Elm Street Dalton, GA 30720Jim Bethelc/o J & J Industries, Inc.818 J & J Drive Dalton, GA 30720 A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 322 of 363 Attachment C Introduction1.1, General Information - 10 CFR 54.19Edwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal1.1-10OfficersJustin RobinsonChairman2203 Druid Lane Dalton, GA 30720Don CopePresident/Chief Executive Officer1200 V. D. Parrott, Jr. Parkway Dalton, GA 30720Todd Reigel Secretaryc/o Paradigm Printing, Inc.

429 Virgil Drive Dalton, GA 307201.1.5 CLASS OF LICENSE, USE OF THE FACILITY, AND PERIOD OF TIME FORWHICH THE LICENSE IS SOUGHTSNC requests a Class 104 operating license for Plant Hatch Unit 1 and a Class 103 operating license for Unit 2 (License Nos. DPR-57 and NPF-5, respectively) for a period 20 years beyond the expiration of the current licenses, midnight, August 6, 2014 for Unit 1 and midnight, June 13, 2018 for Unit 2.Because the current licensing basis is carried forward with the possible exception of someaging issues, Southern Nuclear expects the form and content of the licenses to be generallythe same as they now exist. Southern Nuclear, thus, also requires similar extensions of specific licenses under Parts 30, 40, and 70 that are contained in the current operating licenses.1.1.6 EARLIEST AND LATEST DATES FOR ALTERATIONS, IF PROPOSEDNo physical plant alterations or modifications have been identified as necessary in order to implement the provisions of this application.1.1.7 RESTRICTED DATAWith regard to the requirements of 10 CFR 54.17(f), this application does not contain any Restricted Data, as that term is defined in the Atomic Energy Act of 1954, as amended, or other defense information, and it is not expected that any such information will become involved in these licensed activities.In accordance with the requirements of 10 CFR 54.17(g), the applicants will not permit anyindividual to have access to, or any facility to possess restricted data or classified national security information until the individual and/or facility has been approved for such access under the provisions of 10 CFR Parts 25 and/or 95.1.1.8 REGULATORY AGENCIESThe direct costs incurred by SNC in connection with HNP are billed directly to GPC.

Expenses which are not direct charges to specific plants are allocated to GPC and others for whom the expenses are incurred, as appropriate. GPC recovers a portion of HNP direct and A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 323 of 363 Attachment C Introduction1.1, General Information - 10 CFR 54.19Edwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal1.1-11allocated costs from the other co-owners in relation to their respective ownership interests inHNP, and the remainder through rates. The rates charged and services provided by GPCare subject to the jurisdiction of the Georgia Public Service Commission and the FederalEnergy Regulatory Commission.Georgia Public Service Commission244 Washington St. S.W.

Atlanta, Georgia 30334Federal Energy Regulatory Commission888 First St. N.E.Washington, DC 204261.1.9 LOCAL NEWS PUBLICATIONSNews publications in circulation near Plant Hatch which are considered appropriate to give reasonable notice of the application are as follows:The Baxley News-BannerP.O. Box 409 Baxley, Georgia 31513 912-367-2468Fax-912-367-0277Vidalia Advance-ProgressP.O. Box 669 Vidalia, GA 30474 912-537-4899 Fax-912-537-4899The Tattnall JournalP.O. Box 278 Reidsville, GA 30453 912-557-6761 Fax-912-557-4132The Jeff Davis LedgerP.O. Box 338Hazlehurst, GA 31539 912-375-4225 Fax-912-375-3704The Macon TelegraphP.O. Box 4167Macon, GA 31208 912-744-4200 Fax-912-744-4385Savannah Morning NewsP.O. Box 1088Savannah, GA 31402 A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 324 of 363 Attachment C Introduction1.1, General Information - 10 CFR 54.19Edwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal1.1-12912-236-9511Fax-912-234-65221.1.10 CONFORMING CHANGES TO STANDARD INDEMNITY AGREEMENT10 CFR 54.19(b) requires that each application must include conforming changes to the standard indemnity agreement, 10 CFR 140.92, Appendix B, to account for the expiration term of the proposed renewed license. Article VII of the original Indemnity Agreement, whichwas issued on August 2, 1973, along with the HNP Materials License, provides that theAgreement will terminate at the expiration of the license identified in Item 3 of the Attachment (SNM-1378). Since August 2, 1973, the Indemnity Agreement has been amended from time to time. Two of these amendments added license numbers DPR-57 and NPF-5 to Item 3 of the Attachment. As a consequence of these amendments, the existing Indemnity Agreementis presently due to terminate at midnight, June 13, 2018, as the last of these two licensesexpires. SNC requests that conforming changes be made to Item 3 of the Attachment to the Indemnity Agreement (and any other provision of the Attachment or Indemnity Agreement) to make clear that the Indemnity Agreement is extended until the expiration date of the renewed HNP operating licenses issued by the Commission in response to this application.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 325 of 363 Attachment C

Cracking Mech anisms Matrixby Commodity Group06/20/00 1Commodity Group Fatigue Cracking SCC CrackingIGA Cracking Other CrackingC.2.1.1.1 XXC.2.1.1.2 XXC.2.1.1.3 XC.2.1.1.4XXXC.2.1.1.5XXXC.2.1.1.6C.2.2.1.1 XC.2.2.1.2XXXC.2.2.2.1 XC.2.2.2.2 XC.2.2.2.3C.2.2.3.1 XC.2.2.3.2XXXC.2.2.4.1 XC.2.2.4.2 XC.2.2.5.1 XC.2.2.5.2 XC.2.2.5.3 XC.2.2.6.1 XC.2.2.6.2 XC.2.2.6.3 XC.2.2.6.4 XC.2.2.7.1 XC.2.2.7.2 XC.2.2.8.1 XC.2.2.8.2 XC.2.2.8.3 XC.2.2.9.1 XC.2.2.9.2XXXC.2.2.9.3 XC.2.2.9.4 XC.2.2.10.1C.2.2.10.2C.2.2.11.1XXXC.2.3.1XXXC.2.3.2XXXC.2.3.3XXXC.2.3.4.1 XC.2.3.4.2 XC.2.3.4.3C.2.4.1C.2.4.2C.2.4.3C.2.4.4.1 XXC.2.4.4.2 X A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 327 of 363 Attachment C Cracking Mech anisms Matrixby Commodity Group06/20/00 2Commodity Group Fatigue Cracking SCC CrackingIGA Cracking Other CrackingC.2.5.1C.2.5.2C.2.5.3C.2.5.4C.2.5.5C.2.6.1 XC.2.6.2 XC.2.6.3C.2.6.4C.2.6.5C.2.6.6C.2.6.7 XC.2.6.8 X A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 328 of 363 Attachment C Structures and Components Subject to Aging Management Review2.3, Mechanical Systems Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.3-15Component Groups Requiring an Aging Management ReviewTable 2.3.3-2 Components Supporting Residual Heat Removal System [E11] IntendedFunctions and Their Component FunctionsMechanical ComponentComponent FunctionsMaterialBoltingPressure BoundaryCarbon SteelBoltingPressure BoundaryStainless SteelConductivity ElementFission Product Barrier,Pressure BoundaryStainless SteelHeat Exchanger ChannelAssemblyPressure BoundaryCarbon SteelHeat Exchanger Impingement

PlateShelter/ ProtectionStainless SteelHeat Exchanger- ShellFission Product Barrier,Pressure BoundaryCarbon SteelHeat Exchanger Tube SheetFission Product BarrierPressure BoundaryCarbon Steel Stainless SteelHeat Exchanger TubesFission Product Barrier,Pressure BoundaryStainless Steel PipingFission Product Barrier,Pressure BoundaryCarbon SteelPump CasingsFission Product Barrier,Pressure BoundaryCarbon SteelPump Casings - Bowl AssemblyPressure BoundaryCast Austenitic Stainless Steel Pump Column / DischargeHeadPressure BoundaryCarbon SteelPump Sub BaseStructural SupportCarbon SteelRestricting OrificesFission Product Barrier,Pressure Boundary, FlowRestrictionStainless SteelStrainer BasketDebris ProtectionStainless SteelStrainer BodiesDebris ProtectionCarbon SteelStrainersDebris ProtectionStainless SteelThermowellFission Product Barrier,Pressure BoundaryCarbon SteelTubingPressure BoundaryCopper AlloyValve BodiesPressure BoundaryCarbon Steel A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 329 of 363 Attachment C Structures and Components Subject to Aging Management Review2.3, Mechanical Systems Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.3-60Component Groups Requiring an Aging Management ReviewTable 2.3.4-16Components Supporting Traveling Water Screens/ Trash Rack System[W33] Intended Functions and Their Component FunctionsMechanical ComponentComponent FunctionsMaterialBoltingPressure BoundaryCarbon SteelSight Glasses*Pressure BoundaryCeramicTrash RacksDebris ProtectionCarbon SteelTraveling ScreenDebris ProtectionCarbon SteelStainless SteelCopper Alloy*Valve BodiesPressure BoundaryCarbon Steel* No aging effects requiring management A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 330 of 363 Attachment C Structures and Components Subject to Aging Management Review2.3, Mechanical Systems Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.3-66Component Groups Requiring an Aging Management ReviewTable 2.3.4-18Components Supporting Fire Protection System [X43] Intended Functionsand Their Component FunctionsMechanical ComponentComponent FunctionsMaterialBoltingPressure BoundaryCarbon SteelFire DoorsFire BarrierCarbon SteelGalvanized SteelCopper Alloy Stainless SteelAluminumNonmetallic, Inorganic-Gypsum Fibers, nonasbestos synthetic Nonmetallic, organicFire HydrantsPressure BoundaryCast IronFittingsPressure BoundaryCast IronFittingsPressure BoundaryCopper AlloyCast IronFusible MaterialPressure BoundaryNonferrous MetalKaowool and Hold-down StrapsFire BarrierGalvanized Steel, InsulationmaterialNozzlesFlow RestrictionAluminumCopper AlloyNozzlesFlow RestrictionCopper AlloyPenetration SealsFire BarrierConcreteCeramicsCarbon SteelSynthetic Fiber ElastomersPilot ValvesPressure BoundaryAluminumPipe Line StrainersPressure BoundaryCast Iron PipingPressure BoundaryCarbon SteelAluminum Galvanized Steel Copper Alloy Cast Iron PipingPressure BoundaryCarbon SteelStainless Steel PipingPressure BoundaryCarbon SteelGalvanized SteelPump CasingsPressure BoundaryCast IronRestricting OrificesPressure Boundary, FlowRestrictionStainless SteelSprinkler Head BulbsPressure BoundaryCeramics A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 331 of 363 Attachment C Structures and Components Subject to Aging Management Review2.4, Structures Screening ResultsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal2.4-6Component Groups Requiring an Aging Management ReviewTable 2.4.3-1Components Supporting Primary Containment [T23] Intended Functions andTheir Component FunctionsStructural ComponentComponent FunctionsMaterialAnchors and BoltsStructural Support;Nonsafety Related Structural SupportCarbon Steel Galvanized SteelStainless SteelBlind Flange*Fission Product BarrierCarbon SteelBolting*Fission Product BarrierCarbon SteelContainment Isolation Valves *Fission Product BarrierCarbon SteelContainment Isolation Valves*Fission Product BarrierStainless SteelContainment Penetrations (Mechanical only)Fission Product BarrierCarbon SteelStainless SteelMiscellaneous SteelStructural Support;Radiation Shielding;Pipe Whip Restraint;Nonsafety Related Structural SupportCarbon SteelGalvanized SteelPiping*Fission Product BarrierCarbon SteelPiping*Fission Product BarrierStainless SteelReinforced ConcreteStructural Support;Shelter/Protection;Flood Barrier;Fission Product Barrier;Radiation Shielding;Missile Barrier; HE/ME ShieldingConcrete Carbon SteelSteel Bellows (inside Vent Pipe)Pressure Boundary;Fission Product BarrierCarbon SteelStainless SteelStructural SteelStructural Support;Shelter/Protection;Radiation Shielding;Missile Barrier;HE/ME Shielding; Pipe Whip Restraint;Nonsafety Related Structural Support;Pressure BoundaryFission Product Barrier;Exchange HeatCarbon SteelStainless SteelTubing*Fission Product Barrier; PressureBoundaryStainless SteelUnreinforced ConcreteRadiation ShieldingUnreinforced Concrete**Vent Pipe, Vent Header,DowncomersFission Product Barrier; Pressure BoundaryCarbon Steel*Piping and valves include components from systems P51, P21, T23, G51, G11, D11, and C51. Theseare all included in function T23-01, Torus/Drywell.**No aging effects requiring management A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 332 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-5Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityBolting / C.2.1.1.6(Class 1)Pressure BoundaryFission Product

BarrierInsideCarbon SteelLoss of PreloadTorque ActivitiesInservice Inspection ProgramBolting / C.2.2.10.1(non-Class 1)Pressure Boundary Fission Product BarrierInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings ProgramCrack Growth Monitor /

C.2.1.1.4(Class 1)Pressure Boundary Fission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection Program Component Cyclic or Transient Limit ProgramTreated Water Systems PipingInspectionsFlow Nozzle / C.2.1.1.3(Class 1)Pressure BoundaryFission Product

BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Inservice Inspection Program Galvanic Susceptibility InspectionsComponent Cyclic or Transient Limit ProgramFlow Accelerated Corrosion ProgramTreated Water Systems Piping InspectionsPiping / C.2.2.1.1(non-Class 1)Pressure Boundary Fission Product

BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Galvanic Susceptibility Inspections Treated Water Systems PipingInspectionsFlow Accelerated Corrosion ProgramPiping / C.2.2.1.2(non-Class 1)Pressure Boundary Fission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlTreated Water Systems PipingInspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 333 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-6Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityPiping / C.2.2.2.2(non-Class 1)Pressure BoundaryFission Product

BarrierDemin WaterStainless SteelLoss of MaterialCrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems PipingInspectionsPiping / C.2.2.3.1(non-Class 1)Pressure BoundaryFission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.2.3.2(non-Class 1)Pressure BoundaryFission Product BarrierTorus WaterStainless SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.1.1.3(Class 1)Pressure Boundary Fission Product BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection ProgramGalvanic Susceptibility InspectionsComponent Cyclic or Transient Limit ProgramFlow Accelerated Corrosion ProgramTreated Water Systems PipingInspectionsPiping / C.2.1.1.4(Class 1)Pressure BoundaryFission Product BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlInservice Inspection ProgramComponent Cyclic or Transient Limit

Program Treated Water Systems PipingInspectionsPiping / C.2.2.9.1 (non-Class 1)Pressure BoundaryFission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingInservice Inspection ProgramGas Systems Component InspectionsPassive Component InspectionActivities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 334 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-7Table 3.2.1-2Aging Effects Requiring Management for Components Supporting Nuclear Boiler System [B21] Intended Functions and TheirComponent Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging Effects Aging ManagementProgram/ActivityRestricting Orifice /C.2.1.1.4(Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry ControlComponent Cyclic or Transient Limit ProgramInservice Inspection ProgramTreated Water Systems PipingInspectionsThermowell/

C.2.2.9.1(non-Class 1)Pressure Boundary Fission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingGas Systems Component InspectionsPassive Component InspectionActivitiesThermowell /

C.2.1.1.4 (Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry Control Inservice Inspection Program Component Cyclic or Transient Limit ProgramTreated Water Systems Piping InspectionsValve Bodies / C.2.2.1.1(non-Class 1)Pressure BoundaryFission Product BarrierReactor WaterCarbon SteelLoss of MaterialCrackingReactor Water Chemistry Control Flow Accelerated Corrosion ProgramGalvanic Susceptibility InspectionsTreated Water Systems PipingInspectionsValve Bodies / C.2.2.1.2(non-Class 1)Pressure Boundary Fission Product

BarrierReactor WaterStainless SteelLoss of MaterialCrackingReactor Water Chemistry Control Treated Water Systems Piping InspectionsValve Bodies / C.2.2.9.1 (non-Class 1)Pressure Boundary Fission Product

BarrierWetted GasCarbon SteelLoss of MaterialCrackingGas Systems Component Inspections Inservice Inspection Program Passive Component Inspection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 335 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-14Table 3.2.3-2Aging Effects Requiring Management for Components Supporting Residual Heat Removal System [E11] Intended Functionsand Their Component Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityPump Casings /C.2.2.3.1Fission Product Barrier, Pressure

BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlGalvanic Susceptibility InspectionsTreated Water Systems PipingInspectionsPump Casings - BowlAssembly/ C.2.2.6.2Pressure BoundaryRaw WaterCast AusteniticStainless SteelLoss of Material Flow Blockage CrackingLoss of Heat ExchangerPerformancePSW and RHRSW Inspection Program Plant Service Water and RHR ServiceWater Chemistry Control ProgramStructural Monitoring Program Pump Column /Discharge Head /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of Material Flow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control ProgramStructural Monitoring Program Galvanic Susceptibility InspectionsPump Sub Base /

C.2.4.1Structural SupportInsideCarbon SteelLoss of MaterialProtective Coatings Program Restricting Orifices /C.2.2.3.2Fission Product Barrier, Pressure BoundaryTorus WaterStainless SteelLoss of Material CrackingSuppression Pool Chemistry ControlTreated Water Systems PipingInspectionRestricting Orifices /C.2.2.3.2Fission Product Barrier, Pressure Boundary, FlowRestrictionTorus WaterStainless SteelLoss of Material CrackingSuppression Pool Chemistry ControlTreated Water Systems Piping InspectionRestricting Orifices /

C.2.2.6.2Pressure Boundary, Flow RestrictionRaw WaterStainless SteelLoss of Material Flow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control ProgramStructural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 336 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-15Table 3.2.3-2Aging Effects Requiring Management for Components Supporting Residual Heat Removal System [E11] Intended Functionsand Their Component Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityStrainer Bodies /C.2.2.6.1Debris ProtectionRaw WaterCarbon SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program Plant Service Water and RHR ServiceWater Chemistry Control ProgramGalvanic Susceptibility InspectionsStructural Monitoring ProgramStrainers / C.2.2.3.2Debris ProtectionTorus WaterStainless SteelLoss of Material CrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramThermowell / C.2.2.3.1Fission Product Barrier, Pressure

BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry Control Treated Water Systems PipingInspectionsTubing / C.2.2.6.3Pressure BoundaryRaw WaterCopper AlloyLoss of Material Cracking Flow BlockagePSW and RHRSW Chemistry ControlProgram PSW and RHRSW Inspection Program Structural Monitoring ProgramValve Bodies / C.2.2.3.1Pressure Boundary,Fission Product

BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Galvanic Susceptibility Inspection Treated Water Systems Piping InspectionValve Bodies/ C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of Material Flow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Galvanic Susceptibility InspectionsStructural Monitoring ProgramStrainer Basket/C.2.2.6.2Debris ProtectionRaw WaterStainless SteelLoss of MaterialFlow BlockagePSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control ProgramStructural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 337 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-17Table 3.2.3-4 Aging Effects Requiring Management for Components Supporting High Pressure Coolant Injection System [E41] Intende dFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryFission Product BarrierInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Bolting / C.2.2.10.2Pressure Boundary Fission Product BarrierInsideStainless SteelLoss of PreloadTorque ActivitiesFlexible Connector /

C.2.2.9.2Pressure Boundary Fission Product Barrier Dry Wetted GasStainless SteelCrackingLoss of MaterialGas Systems Component InspectionsPiping / C.2.2.1.1Pressure Boundary Fission Product BarrierReactor WaterCarbon SteelLoss of Material CrackingReactor Water Chemistry ControlGalvanic Susceptibility InspectionsFlow Accelerated Corrosion ProgramTreated Water Systems Piping InspectionsPiping / C.2.2.2.1Pressure BoundaryFission Product BarrierDemin WaterCarbon SteelLoss of Material CrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems PipingInspectionsPiping / C.2.2.2.2Pressure Boundary Fission Product BarrierDemin WaterStainless SteelLoss of Material CrackingDemineralized Water and Condensate Storage Tank Chemistry Control Program Treated Water Systems Piping InspectionsPiping / C.2.2.3.1Pressure Boundary Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry ControlGalvanic Susceptibility Inspections Treated Water Systems PipingInspectionsTorus Submerged Components Inspection

Program Protective Coatings ProgramPiping / C.2.2.3.2Pressure Boundary Fission Product BarrierTorus WaterStainless SteelLoss of Material CrackingSuppression Pool Chemistry Control Torus Submerged Components Inspection Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 338 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-25Table 3.2.3-5Aging Effects Requiring Management for Components Supporting Reactor Core Isolation Cooling System [E51] IntendedFunctions and Their Component Functions (Continued)Mechanical Component Component FunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityValve Bodies / C.2.2.9.2Pressure BoundaryFission Product

BarrierWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component Inspections Passive Component Inspection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 339 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-28Table 3.2.3-7Aging Effects Requiring Management for Components Supporting Primary Containment Purge and Inerting System [T48] IntendedFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryInsideCarbon SteelLoss of Preload Loss of MaterialTorque ActivitiesProtective Coatings Program Bolting / C.2.2.10.2Pressure BoundaryInsideStainless SteelLoss of Preload Torque Activities Flex Hose / C.2.2.9.1Pressure BoundaryAirStainless SteelCrackingGas Systems Component InspectionsNitrogen Tank Jacket / C.2.2.9.1Structural SupportAirCarbon SteelCrackingLoss of MaterialGas Systems Component InspectionsPassive Component InspectionActivitiesPiping / C.2.2.3.1Pressure BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlGalvanic Susceptibility InspectionsTorus Submerged ComponentsInspection ProgramProtective Coatings ProgramPiping / C.2.2.3.1Pressure BoundaryTorus WaterCarbon SteelLoss of Material CrackingSuppression Pool Chemistry ControlTorus Submerged ComponentsInspection ProgramPiping / C.2.2.3.2Pressure BoundaryTorus WaterStainless SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Treated Water Systems PipingInspectionsPiping / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone RequiredPiping / C.2.2.9.1Pressure BoundaryWetted GasCarbon SteelCrackingLoss of MaterialGas Systems Component Inspections Passive Component InspectionActivitiesPressure Buildup Coil / C.2.2.8.2Pressure BoundaryExchange Heat Dried GasStainless SteelCrackingNone RequiredRupture Disc / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone RequiredStorage Tank / C.2.2.8.2Pressure BoundaryDried GasStainless SteelCrackingNone Required A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 340 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-33Table 3.2.4-2Aging Effects Requiring Management for Components Supporting Refueling Platform Equipment Assembly [F15] IntendedFunctions and Their Component FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityAnchors and Bolts C.2.6.3Structural support Nonsafety Related Structural SupportInsideCarbon steelLoss of materialProtective Coatings Program Overhead Crane and Refueling PlatformInspectionStructural Monitoring ProgramMiscellaneous Steel C.2.6.3Structural support;Nonsafety RelatedStructural SupportInsideCarbon steelLoss of materialProtective Coatings ProgramOverhead Crane and Refueling Platform Inspection Structural Monitoring ProgramRivetsStructural SupportInsideAluminumNoneNone RequiredStructural Steel

C.2.6.3Structural supportInsideCarbon steelLoss of materialProtective Coatings ProgramOverhead Crane and Refueling Platform InspectionStructural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 341 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-38Table 3.2.4-7Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions a ndTheir Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityBolting /C.2.2.10.1Pressure BoundaryOutside, InsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Flexible Connector /

C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramStructural Monitoring ProgramPiping / C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control ProgramStructural Monitoring Program Galvanic Susceptibility InspectionsPiping / C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control Program Structural Monitoring ProgramPump Bowl Assembly /

C.2.2.6.2Pressure BoundaryRaw WaterCast AusteniticStainless SteelLoss of Material Flow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Structural Monitoring ProgramPump Discharge Column /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Structural Monitoring ProgramPump Discharge Head / C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

ProgramStructural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 342 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-39Table 3.2.4-7Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions a ndTheir Component Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityPump Sub Base /

C.2.4.1Structural SupportInsideCarbon SteelLoss of MaterialProtective Coatings Program Restricting Orifices /

C.2.2.6.2Pressure Boundary, Flow RestrictionRaw WaterStainless SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramStructural Monitoring ProgramSight Glass Body

/ C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageGalvanic CorrosionCrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control ProgramStructural Monitoring ProgramSight Glass Body/C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control ProgramStructural Monitoring ProgramStrainer /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control Program Structural Monitoring ProgramStrainer /C.2.2.6.4Pressure BoundaryRaw WaterGray Cast IronLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control Program Structural Monitoring ProgramStrainer Basket /

C.2.2.6.2Debris ProtectionRaw WaterStainless SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Structural Monitoring ProgramStrainer Basket /

C.2.2.6.4Debris ProtectionRaw WaterGray Cast IronLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Structural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 343 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-40Table 3.2.4-7Aging Effects Requiring Management for Components Supporting Plant Service Water System [P41] Intended Functions a ndTheir Component Functions (Continued)Mechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityThermowell /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialCrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramThermowell /

C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialCrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control ProgramValve Bodies /C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control ProgramStructural Monitoring ProgramGalvanic Susceptibility InspectionsValve Bodies /C.2.2.6.2Pressure BoundaryRaw WaterStainless SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection ProgramPSW and RHRSW Chemistry Control Program Structural Monitoring ProgramValve Bodies /

C.2.2.6.3Pressure BoundaryRaw WaterCopper AlloyLoss of MaterialCracking Flow BlockagePSW and RHRSW Chemistry Control

Program Structural Monitoring Program PSW and RHRSW Inspection ProgramVenturi /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow Blockage CrackingPSW and RHRSW Inspection Program PSW and RHRSW Chemistry Control

Program Structural Monitoring ProgramGalvanic Susceptibility Inspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 344 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-47Table 3.2.4-13Aging Effects Requiring Management for Components Supporting Reactor Building Crane [T31] Intended Functions and TheirComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityStructural Steel/

C.2.6.3Structural SupportInsideCarbon SteelLoss of MaterialOverhead Crane and Refueling PlatformInspectionProtective Coatings Program Structural Monitoring Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 345 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-50Table 3.2.4-16Aging Effects Requiring Management for Components Supporting Traveling Water Screens / Trash Rack System [W33] IntendedFunctions and Their Component FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityTrash Rack /

C.2.6.3Debris ProtectionSubmergedCarbon SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings Program Traveling Screen /

C.2.6.3Debris ProtectionSubmergedCarbon SteelStainless SteelLoss of MaterialStructural Monitoring ProgramTraveling Screen /

C.2.6.3Debris ProtectionSubmergedCopper AlloyNoneNone RequiredValve Bodies /

C.2.2.6.1Pressure BoundaryRaw WaterCarbon SteelLoss of MaterialFlow BlockageCrackingPSW and RHRSW Inspection Program Plant Service Water and RHR Service WaterChemistry Control ProgramGalvanic Susceptibility InspectionsBolting / C.2.2.10.1Pressure BoundaryOutsideCarbon SteelLoss of MaterialLoss of PreloadTorque Activities Protective Coatings Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 346 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-52Table 3.2.4-18Aging Effects Requiring Management for Components Supporting Fire Protection System [X43] Intended Functions and TheirIntended FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBoltings / C.2.2.10.1Pressure BoundaryInsideOutsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Fire Doors / C.2.3.4.3Fire BarrierInsideCarbon SteelLoss of MaterialFire Protection ActivitiesFire Doors / C.2.3.4.3Fire BarrierInsideGalvanized SteelCopper AlloyStainless Steel AluminumNonmettalic,Inorganic Gypsum

Fibers, NonasbestosSyntheticNonmetallic, OrganicNoneNone RequiredFire Hydrants / C.2.3.1Pressure BoundaryRaw WaterCast IronLoss of MaterialCracking Flow BlockageFire Protection ActivitiesFittings / C.2.3.1Pressure BoundaryRaw Water AirCast IronLoss of MaterialCracking Flow BlockageFire Protection ActivitiesFittings / C.2.3.3Pressure BoundaryAirCopper AlloyCast IronCracking Loss of MaterialFire Protection ActivitiesFusible Material / C.2.3.1Pressure BoundaryInsideNonferrous MetalLoss of MaterialCrackingFire Protection ActivitiesKaowool and Hold-Down Straps / C.2.3.4.3C.2.3.4.2Fire BarrierInsideGalvanized SteelInsulation MaterialCrackingLoss ofMaterialChange in MaterialPropertiesFire Protection Activities A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 347 of 363 Attachment C Aging Management Review Results3.2, Mechanical SystemsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.2-56Table 3.2.4-19Aging Effects Requiring Management for Components Supporting Fuel Oil System [Y52] Intended Functions and TheirComponent FunctionsMechanical Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityBolting / C.2.2.10.1Pressure BoundaryInsideCarbon SteelLoss of PreloadLoss of MaterialTorque ActivitiesProtective Coatings Program Discharge Head /C.2.2.7.1Pressure BoundaryFuel OilCarbon SteelLoss of MaterialCrackingDiesel Fuel Oil TestingFlex Hose / C.2.2.7.2Pressure BoundaryFuel OilStainless SteelLoss of MaterialCrackingDiesel Fuel Oil TestingManway Shell /

C.2.2.9.1Shelter/ ProtectionAirCarbon SteelCrackingLoss of MaterialGas Systems ComponentInspectionsPassive Component InspectionActivitiesPiping / C.2.2.7.1Pressure BoundaryFuel OilCarbon SteelLoss of MaterialCrackingDiesel Fuel Oil TestingPiping / C.2.2.7.2Pressure BoundaryFuel OilStainless SteelLoss of MaterialCrackingDiesel Fuel Oil TestingPiping / C.2.2.9.1Pressure BoundaryAirCarbon SteelLoss of MaterialCrackingGas Systems Component Inspection Passive Component Inspection ActivitiesPiping / C.2.2.9.2Pressure BoundaryAirStainless SteelCrackingLoss of MaterialGas Systems Component InspectionsPump / C.2.2.7.1Pressure BoundaryFuel OilCarbon SteelLoss of MaterialCrackingDiesel Fuel Oil TestingStrainer Basket /

C.2.2.7.2Shelter/ ProtectionFuel OilStainless SteelLoss of MaterialCrackingDiesel Fuel Oil TestingTank / C.2.2.7.1Pressure BoundaryFuel OilCarbon SteelCrackingLoss of MaterialDiesel Fuel Oil Testing A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 348 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-4Table 3.3.1-3Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Thei rComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging Management Program/ActivityAnchors and Bolts /

C.2.6.2Structural Support; Nonsafety Related Structural SupportContainment Atmosphere; Embedded; Inside Torus WaterCarbon Steel Galvanized Steel Stainless SteelLoss of MaterialProtective Coatings Program Inservice Inspection ProgramSuppression Pool Chemistry ControlBlind Flange* /C.2.2.3.1Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialCrackingSuppression Pool Chemistry Control Treated Water Systems Piping InspectionsContainment IsolationValves* / C.2.2.2.2Fission Product BarrierDemin WaterStainless SteelLoss of MaterialCrackingDemineralized Water and CondensateStorage Tank Chemistry ControlTreated Water Systems Piping InspectionsContainment Isolation Valves* / C.2.2.3.1Fission Product BarrierDemin WaterCarbon SteelLoss of MaterialCrackingDemineralized Water and Condensate Storage Tank Chemistry ControlTreated Water Systems Piping InspectionsContainment IsolationValves* / C.2.2.3.1Fission Product BarrierTorus WaterCarbon SteelLoss of MaterialSuppression Pool Chemistry ControlTreated Water Systems Piping InspectionsContainment Isolation Valves* /

C.2.2.6.2C.2.6.2Fission Product BarrierRaw WaterCarbon SteelLoss of MaterialCrackingPassive Component Inspection ActivitiesContainment Isolation Valves* / C.2.2.9.1Fission Product BarrierWetted GasCarbon SteelLoss of MaterialGas Systems Component InspectionsPassive Component Inspection ActivitiesContainment Isolation Valves* / C.2.2.9.2Fission Product BarrierWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component InspectionContainmentPenetrations(Mechanical only) /

C.2.6.2Fission Product BarrierContainmentAtmosphere; Embedded; InsideCarbon SteelStainless SteelLoss of MaterialProtective Coatings ProgramInservice Inspection ProgramPrimary Containment Leakage Rate Testing Program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 349 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-6Table 3.3.1-3Aging Effects Requiring Management for Components Supporting Primary Containment [T23] Intended Functions and Thei rComponent Functions (Continued)Structural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityStructural Steel /

C.2.6.2Structural Support; Shelter/Protection; Pressure Boundary; Radiation Shielding;Nonsafety RelatedStructural Support; HE/ME Shielding; Missile Barrier;Pipe Whip Restraint;Fission Product

Barrier; Exchange HeatContainment Atmosphere; Inside; Torus Water;EmbeddedCarbon SteelStainless SteelLoss of Material CrackingProtective Coatings Program Primary Containment Leakage RateTesting ProgramInservice Inspection ProgramSuppression Pool Chemistry ControlComponent Cyclic or Transient Limit ProgramTubing* / C.2.2.9.2Fission Product Barrier;Pressure BoundaryWetted GasStainless SteelLoss of MaterialCrackingGas Systems Component InspectionsVent Pipe, VentHeader, Downcomers /

C.2.6.2Pressure BoundaryFission Product BarrierContainment Atmosphere;High Humidity; Inside; Torus WaterCarbon SteelLoss of MaterialCrackingProtective Coatings ProgramInservice Inspection ProgramPrimary Containment Leakage Rate Testing Program Component Cyclic or Transient Limit ProgramSuppression Pool Chemistry ControlBolting / C.2.2.10.1Pressure BoundaryInsideContainment AtmosphereCarbon SteelLoss of MaterialLoss of PreloadProtective Coatings ProgramTorque Activities* Piping and valve bodies include components from systems P51, P21, T23, G51, G11, D11, and C51. These are all included in function T23-01, Torus/Drywell.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 350 of 363 Attachment C Aging Management Review Results3.3, Civil/StructuralEdwin I. Hatch Nuclear PlantFebruary 2000Application for License Renewal3.3-8Table 3.3.1-5Aging Effects Requiring Management for Components Supporting Reactor Building [T29] Intended Functions and TheirComponent FunctionsStructural Component ComponentFunctionsEnvironmentMaterialAging EffectsAging ManagementProgram/ActivityAnchors and Bolts /

C.2.6.3Structural Support;Nonsafety RelatedStructural SupportInside; OutsideCarbon SteelLoss of MaterialProtective Coatings Program Structural Monitoring ProgramBlowout Panels /

C.2.6.6Structural Support;Fission Product BarrierInsideAluminum NoneNone RequiredMiscellaneous Steel /

C.2.6.3Structural Support; HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideCarbon SteelGalvanized SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings ProgramMiscellaneous Steel /

C.2.6.3Structural Support; HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideStainless SteelNoneNone RequiredPanel Joint Seals andSealants / C.2.6.7Shelter/Protection;Fission Product BarrierInside; OutsideElastomers;Nonmetallic,InorganicMaterial PropertyChanges andCracking Loss of AdhesionStructural Monitoring ProgramProtective Coatings ProgramReinforced Concrete C.2.6.1Structural Support; Fire Barrier;Shelter/Protection; Flood Barrier;Fission Product Barrier;Radiation Shielding;Missile Barrier;HE/ME Shielding;Nonsafety RelatedStructural SupportInside; OutsideConcreteMasonry Block Carbon SteelLoss of MaterialCrackingStructural Monitoring Program Protective Coatings ProgramStructural SteelC.2.6.3Structural Support; Missile Barrier;Nonsafety RelatedStructural SupportInside; Outside; SubmergedCarbon Steel Galvanized SteelStainless SteelLoss of MaterialStructural Monitoring ProgramProtective Coatings Program Overhead Crane and Refueling PlatformInspections A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 351 of 363 Attachment C Identification of CommoditiesC.2, Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License RenewalC.2-1C.2 AGING MANAGEMENT REVIEWSSection C.2 of Appendix C provides an aging management summary for each uniquestructure, component, or commodity group at Plant Hatch determined to require agingmanagement during the period of extended operation. This summary includes identificationof aging effects requiring management, aging management programs utilized to manage these aging effects, and a demonstration as to how the identified aging management programs manage aging effects requiring management using attribute tables. Section C.1 ofthe LRA provides discussion of aging effects and environments. Appendix A of the LRAprovides descriptions of aging management programs required to manage aging effectsrequiring management.C.2.1 AGING MANAGEMENT REVIEWS FOR CLASS 1 MECHANICAL DISCIPLINECOMMODITIESC.2.1.1 Class 1 Components Environment DescriptionClass 1 components are subject to an environment of reactor water under normal conditions.The reactor water environment is defined in section C.1.2.1

.C.2.1.1.1Aging Management Review for the Reactor Pressure VesselThe reactor pressure vessel (RPV) consists of the following components:

• Shell and closure heads

• Nozzles, Appurtenances, and Penetrations

• Attachments and connecting welds (brackets and lugs)

• RPV head closure studsThe RPV and associated components are constructed from carbon steel, low alloy steel,austenitic stainless steel, and nickel based alloys.SystemsB11 - Reactor Assembly (2.3.1.1)Aging Effects Requiring Management

• Cracking (C.1.2.1.2) due to stress corrosion cracking (SCC) and fatigue. The SCC agingeffect does not apply to the CRD stub tubes and the low alloy and carbon steel reactorvessel safe ends.

• Loss of fracture toughness (C.1.2.1.3) due to neutron embrittlement.A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links.Aging Management Programs Aging management programs determined to manage aging effects requiring managementare as follows:

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 352 of 363 Attachment C Identification of CommoditiesC.2, Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License RenewalC.2-9C.2.1.1.2Aging Management Review for the Reactor Pressure Vessel InternalsThe reactor pressure vessel internals requiring an aging management review consist of thefollowing components:

• Shroud and repair hardware

• Shroud support

• Core spray spargers and internal piping

• Top guide - Unit 1 only (Unit 2 has wedges and will not lift even with completely crackedholddown assemblies)

• CRD housing and control rod guide tubes

• Jet pump assembliesThe reactor pressure vessel internals (RPV Internals) are constructed from carbon low alloysteel, cast, wrought, and forged austenitic stainless steels, and nickel based alloys.SystemsB11 - Reactor Assembly (2.3.1.1)Aging Effects Requiring Management

• Cracking (C.1.2.1.2) due to stress corrosion cracking (SCC) and fatigue. The SCC agingeffect is not applicable to the low alloy steel reactor assembly shroud supports.Aging Management Programs Aging management programs determined to manage aging effects requiring managementare as follows:

• Reactor Water Chemistry Control (A.1.1)* Inservice Inspection Program (ISI Program) (A.1.9)* Boiling Water Reactor Vessel Internals Program (BWRVIP) (A.1.15)A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links.Demonstration of Aging ManagementWhat follows is a demonstration that the aging effects requiring management identified will beadequately managed during the period of extended operation.Management of Cracking due to Stress Corrosion CrackingReactor Water Chemistry Control serves to manage cracking due to SCC by controllingelectrochemical corrosion potential (ECP) in accordance with the recommendations of EPRIBWR water chemistry guidelines. This can be accomplished through the use of filter /demineralizers which limit halides and other impurities within the feedwater and hydrogen A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 353 of 363 Attachment C Identification of CommoditiesC.2, Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License RenewalC.2-60C.2.2.3 Non-Class 1 Components Suppression Pool Water Environment DescriptionComponents within section C.2.2.3 are subject to an environment of suppression pool waterunder normal conditions. The suppression pool water environment is defined in sectionC.1.2.2.C.2.2.3.1Aging Management Review for Non-Class 1 Carbon Steel Components Within theSuppression Pool EnvironmentThis commodity group consists of carbon steel commodities with an internal environment ofsuppression pool water or submerged within the suppression pool. The following component types are included within this evaluation:

• Piping* Valve bodies

• Pump casings

• Thermowells

• Blind flangeSystemsB21 - Nuclear Boiler (2.3.1.2)

• E11 - Residual Heat Removal (2.3.3.2)

• E21 - Core Spray (2.3.3.3)

• E41 - High Pressure Coolant Injection (2.3.3.4)

• E51 - Reactor Core Isolation Cooling (2.3.3.5)

• T23 - Primary Containment (2.4.3)* T48 - Primary Containment Purge and Inerting (2.3.3.7)Aging Effects Requiring Management

• Loss of material (C.1.2.2.1) due to general corrosion, galvanic corrosion, crevicecorrosion, pitting, microbiologically influenced corrosion (MIC), and erosion corrosion.

• Cracking (C.1.2.2.2) due to thermal fatigue.A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links.Aging Management ProgramsAging management programs determined to manage aging effects requiring managementare as follows:

• Suppression Pool Chemistry Control (A.1.7)* Protective Coatings Program (A.2.3)A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 354 of 363 Attachment C Identification of CommoditiesC.2, Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License RenewalC.2-87C.2.2.6 Non-Class 1 Components River Water Environment DescriptionRiver water consists of water taken directly from the Altamaha River for use as cooling waterfor various systems. See section C.1.2.4 for a description of the river water environment.C.2.2.6.1Aging Management Review for Non-Class 1 Carbon Steel Components Within the RiverWater EnvironmentThis commodity group includes carbon steel components exposed to an internal environmentof river water. The following component types are included within this evaluation:

• Piping* Valve bodies

• Strainer bodies

• Discharge venturies

• Sight glass bodies

• Thermowells

• Pump discharge columns

• Pump discharge headsSystems* W33 - Traveling Water Screen, Trash Racks (2.3.4.16)

• P41 - Plant Service Water (2.3.4.7)

• E11 - Residual Heat Removal (2.3.3.2)Aging Effects Requiring Management

• Loss of material (C.1.2.4.1) due to general corrosion, galvanic corrosion, erosioncorrosion, crevice corrosion, pitting, microbiologically influenced corrosion (MIC), andfouling.* Cracking (C.1.2.4.2) due to thermal fatigue. This aging effect is not applicable to the E11and P41 pump discharge columns/discharge heads in this environment since thecomponents are submerged in river water and are free to expand or contract.

• Flow blockage (C.1.2.4.3) due to fouling.A complete discussion of aging effect determination is found in section C.1 or by following theabove links.Aging Management ProgramsAging management programs determined to manage aging effects requiring managementare as follows:

• PSW and RHRSW Chemistry Control (A.1.4)* PSW and RHRSW Inspection Program (A.1.13)A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 355 of 363 Attachment C Identification of CommoditiesC.2, Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License RenewalC.2-92C.2.2.6.2Aging Management Review for Non-Class 1 Stainless Steel Components Within theRiver Water EnvironmentThis commodity group includes stainless steel and cast austenitic stainless steel componentswith an internal environment of river water. The following component types are included within this evaluation:

• Piping* Tubing* Restricting orifices

• Thermowells

• Strainer baskets

• Flexible connectors

• Valve bodies

• Pump bowl assemblies

• Site glass bodySystems* E11 - Residual Heat Removal System (2.3.3.2)

• P41 - Plant Service Water (2.3.4.7)Aging Effects Requiring Management

• Loss of material (C.1.2.4.1) due to crevice corrosion, pitting, microbiologically influencedcorrosion (MIC), and fouling.

• Cracking (C.1.2.4.2) due thermal fatigue. This aging effect is not applicable to the P41strainer baskets and the E11 and P41 pump bowl assemblies in this environment sincethe components are submerged in river water and are free to expand or contract.

• Flow blockage (C.1.2.4.3) due to fouling.A complete discussion of aging effect determination is found in section C.1 or by following theabove links.Aging Management ProgramsAging management programs determined to manage aging effects requiring managementare as follows:

• PSW and RHRSW Chemistry Control (A.1.4)* PSW and RHRSW Inspection Program (A.1.13)* Structural Monitoring Program (A.2.5)A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 356 of 363 Attachment C Identification of CommoditiesC.2, Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License RenewalC.2-101C.2.2.6.4Aging Management Review for Non-Class 1 Gray Cast Iron Components Within theRiver Water EnvironmentThis commodity group includes gray cast iron components with an internal environment ofriver water. The following component types are included within this evaluation:

• Strainers and Strainer BasketsSystemsP41 - Plant Service Water (2.3.4.7)Aging Effects Requiring Management

• Loss of material (C.1.2.4.1) due to crevice corrosion, pitting, general corrosion,microbiologically influenced corrosion (MIC), selective leaching, erosion corrosion,galvanic corrosion, and fouling.

• Cracking (C.1.2.4.2) due to thermal fatigue. This aging effect is not applicable to thestrainer baskets since the components are submerged in this environment and are free toexpand or contract.

• Flow blockage (C.1.2.4.3) due to fouling.A complete discussion of aging effect determination is found in section C.1 or by following theabove links.Aging Management ProgramsAging management programs determined to manage aging effects requiring managementare as follows:

• PSW and RHRSW Chemistry Control (A.1.4)* PSW and RHRSW Inspection Program (A.1.13)* Structural Monitoring Program (A.2.5)A complete discussion of the applicable aging management programs may be found inAppendix A of the LRA or by using the above links.Demonstration of Aging ManagementWhat follows is a demonstration that the aging effects requiring management identified will beadequately managed during the period of extended operation.Management of Loss of Material and Flow BlockagePSW and RHRSW Chemistry Control Program provides for treatment with sodiumhypochlorite and sodium bromide. Both sodium hypochlorite and sodium bromide are batchadded (shock treatment) to the PSW Systems as required. These additions are intended to minimize MIC and macroorganism intrusion within service water systems.The PSW and RHRSW Inspection Program addresses loss of material and flow blockage andimplements Plant Hatchs commitment with regard to Generic Letter 89-13. This program A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

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SHEET 357 of 363 Attachment C Identification of CommoditiesC.2, Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License RenewalC.2-105C.2.2.7 Non-Class 1 Components Fuel Oil Environment DescriptionComponents within section C.2.2.7 are subject to an environment of fuel oil under normalconditions. The fuel oil environment is described in section C.1.2.5

.C.2.2.7.1Aging Management Review for Non-Class 1 Carbon Steel Components Within the FuelOil EnvironmentThis commodity group includes carbon steel exposed to an internal environment of fuel oil.The following component types are included within this evaluation:

• Large and small bore piping

• Valve bodies

• EDG transfer pump

• EDG day tanks

• EDG storage tanks

• EDG transfer pump discharge headSystemsY52 - Fuel Oil (2.3.4.19)Aging Effects Requiring Management

• Loss of material (C.1.2.5.1) due to general corrosion, galvanic corrosion, crevicecorrosion, pitting, and MIC.

• Cracking (C.1.2.5.2) due to thermal fatigue. This aging effect is not applicable to theEDG storage tanks since the tanks are underground and temperature fluctuations areinsignificant.A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links.Aging Management Programs Aging management programs determined to manage aging effects requiring managementare as follows:

• Diesel Fuel Oil Testing (A.1.3)A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links.Demonstration of Aging ManagementWhat follows is a demonstration that the aging effects requiring management identified will beadequately managed during the period of extended operation.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

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SHEET 358 of 363 Attachment C Identification of CommoditiesC.2, Aging Management ReviewsEdwin I. Hatch Nuclear PlantFebruary 2000Application for License RenewalC.2-108C.2.2.7.2Aging Management Review for Non-Class 1 Stainless Steel Components Within theFuel Oil EnvironmentThis commodity group includes stainless steel components exposed to an internalenvironment of fuel oil. The following component types are included within this evaluation:

• Piping* Flexible hose

• Strainer baskets

• Valve bodiesSystemsY52 - Fuel Oil (2.3.4.19)Aging Effects Requiring Management

• Loss of material (C.1.2.5.1) due to crevice corrosion, pitting, and microbiologicallyinfluenced corrosion (MIC).

• Cracking (C.1.2.5.2) due to thermal fatigue. This aging effect is not applicable to thestrainer baskets since the components are submerged in fuel oil.A complete discussion of the applicable aging effect determinations may be found in section C.1 of the LRA or by using the above links.Aging Management ProgramsAging management programs determined to manage aging effects requiring managementare as follows:

• Diesel Fuel Oil Testing (A.1.3)A complete discussion of the applicable aging management programs may be found in Appendix A of the LRA or by using the above links.Demonstration of Aging ManagementWhat follows is a demonstration that the aging effects requiring management identified will beadequately managed during the period of extended operation.Management of Loss of Material due to General Corrosion, Galvanic corrosion, Pitting,Crevice Corrosion, and MICDiesel Fuel Oil Testing provides for sampling and analysis of fuel oil deliveries for water andsediment contamination. Biocides are also added at this time in order to minimize thepotential for MIC within components. Water and sediment contamination levels within storage tanks are checked on a regular basis to assure that no significant buildup of contaminants exists. If excessive contamination does occur, the program provides fordraining and cleaning of the tank as required to reestablish and maintain acceptablecontaminant levels. Fuel oil is also tested for proper viscosity and specific gravity, thereby A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

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SHEET 359 of 363 Attachment C

PART 1 OF RAI - 2.3.4 - FPS - 3:

Exclusion of certain fire protection components from the scope of license renewal and from an aging management review

1. Dedicated Storage Tanks

(a) The applicant states in LRA Section 2.3.4.18, that the water supply for the fire protection system inside the protected area is provided by two 300,000 gallon dedicated storage tanks. Each tank is supplied by two deep wells, each with a 700 gpm makeup pump capable of refilling either tank within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Flow diagram Volume 1, HL-11033, Sheet 1, Fire Protection Piping P&ID Pumphouse Layout, shows that the tank fill line is not highlighted to include this piping within the scope of license renewal. This piping appears to provide water from underground wells to the dedicated storage tanks. Justify the exclusion of this piping from within the scope of license renewal.

(b) Flow diagram Volume 1, HL-11033, Sheet 1, Fire Protection Piping P&ID Pumphouse Layout, does not show the pumps which draw water from the wells. Since these wells supply the dedicated storage tanks with water for use by the fire protection system, discuss if these pumps (casings) should also be included within the scope of license renewal and subject to

an AMR. RESPONSE TO PART 1 OF RAI - 2.3.4 - FPS - 3 (Revised 9/28/00):

As described in the response to RAI 2.3.4-FPS-1, FHA section 9.2 Appendix B identifies the SSCs required to protect safety related or safe shutdown components from the effects of fire, and these SSCs are in scope for license renewal. The well water supply system is not relied upon in FHA section 9.2 Appendix B, and is therefore not in the scope of license renewal.

As discussed in a 9/28/00 telecon with NRC, the intent of the well water supply system is not to fight a fire, but to maintain level in the two redundant, 100% capacity each, fire water storage tanks which are maintained at a prescribed level by surveillance requirements. There is sufficient capacity in one tank, at the minimum surveillance level, to quench the design basis fire. The well water supply system is capable of refilling either tank in a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, as specified by regulatory requirements. The fill line connects to each tank at the roof such that a break in this line would not drain the associated tank.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 361 of 363 Attachment C PART 5 OF RAI - 2.3.4 - FPS - 3:

Exclusion of certain fire protection components from the scope of license renewal and from an aging management review

5. System filters, fire extinguishers, fire hoses, and air packs:

System filters, fire extinguishers, fire hoses, and air packs are not included within the scope of license renewal and are not subject to an AMR. (In a July 6, 2000 phone call, the applicant clarified that systems filters were included within scope and are subject to an AMR. However, in the LRA, they are listed as strainers in Table 2.3.4-18). As a result of the staffs experience with license renewal, the staff has found that fire extinguishers, fire hoses, and air packs (within the scope of license renewal) may be excluded, on a plant-specific basis, from an aging management review under 10 CFR 54.21(a)(1)(ii). These components are considered within the scope of license renewal and are typically replaced based on specific performance and condition monitoring activities that clearly establish a routine replacement practice based on a qualified life component. These components may be excluded based on specific performance and condition monitoring activities provided that the applicant (1) identifies and lists in the LRA each component type subject to such replacement, and (2) identifies the applicable programs that conform to appropriate standards (e.g., for fire protection components -applicable NFPA standards and 42 CFR Part 84). Justify the exclusion of these components from the scope of license renewal and an AMR.

RESPONSE TO PART 5 OF RAI - 2.3.4 - FPS - 3 (Revised 9/28/00):

Pursuant to discussions held with NRC during the scoping inspection performed September 11, 2000 through September 15, 2000, the following revised response to this

RAI is provided.

Filters are identified as strainers in the fire protection system. There are two types of strainers used in the fire protection system: Y-strainers and pipe line basket strainers. Both types are subject to aging management and are included in scope for license

renewal.

Fire extinguishers, air packs, and CO 2 hoses are short lived components based on replacement intervals per site approved procedures, and are therefore not subject to AMR. The replacement intervals established by plant procedures are as follows: CO 2 fire extinguisher replacement every 5 years, and dry chemical fire extinguisher replacement every 12 years; air pack replacement every 15 years; CO 2 hose replacement every 5 years. The plant procedures also specify inspection and testing intervals. Water fire hoses are condition and performance monitored routinely, and replaced based on degradation criteria specified in a site-approved procedure, and are therefore not subject to AMR. By plant procedure, water fire hoses are to be unracked, visually inspected, and hydrostatically tested every 2 years. Water fire hoses that do not meet the inspection or hydrostatic test criteria are replaced. Water fire hoses were inadvertently omitted from Table 3.2.4-18.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

SUMMARY

SHEET 362 of 363 Attachment C RAI - 2.3.4 - FPS - 10:

LRA Section A.2.1.3 states that the fire protection system design was reviewed against the applicab le NFPA codes. NFPA 25, Section 2.3.3.1, Sprinklers, stat es that where sprinkler s h ave been in place for 50 years, they shall be replaced or repr esentative samples from one or more sample areas shall be submitted to a recog nized test in g laboratory for field service testing. As part of the fire protection license renewal programs at Hatch, discuss if NFPA 25 will be implemented to ensure that any aging effects have not degraded the sprinkler and its components from the original performance criteria as intended by the listing. If NFPA 25 will not be implemented at Hatch, provide justification and evidence that other means to detect aging of sprinklers, equivalent to NFPA 25, are available through plant-specific programs and procedures.

RESPONSE TO RAI - 2.3.4 - FPS - 10 (Revised 9/28/00):

Pursuant to discussions held with NRC during the scoping inspection performed

September 11, 2000 through September 15, 2000, the following revised response to this RAI is provided.

Although Plant Hatch uses NFPA 25 as general design guidance, Plant Hatch is not committed to compliance with it. Plant Hatch is committed to regulatory requirements as described in the FHA. Thus, in a manner consistent with the guidance of NFPA 25, a one-time inspection will be performed at, or before, 50 years of service lif e for sprinkler heads in the scope of license renewal. A random sampling of each type of sprinkler head in the scope of license renewal will be submitted to a recognized laboratory for testing. Based on the results, corrective actions would be accomplished, if required, to assure continued sprinkler head function during the period of extended operation.

Appendix B, Section 2.1, descibes this one-time inspection which is called Sprinkler Head Inspections. Periodic condition and performance monitoring of sprinkler heads is also performed by the fire protection activities.

A-47039 LICENSE RENEWAL AGING MANAGEMENT REVIEW

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SHEET 363 of 363 Attachment C

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