ML070430094

E. I. Hatch, Unit 2, Volume 2, Revision 1, Class 1, 2 and 3 Components Fourth Ten-Year Examination Plan.

ML070430094
Person / Time
Site:	Hatch
Issue date:	11/20/2006
From:	Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML070430094 (564)

Text

HATCH UNIT 2 FOURTH INTERVAL EXAMINATION PLANS CLASS, 1, 2, AND 3 COMPONENTS DISTRIBUTION H2 VOL2 DIST.doc Page 1 of 1 Rev. 1

Manual Manual Holder Number 1 Document Control QA Record Hatch Unit 2 Fourth Interval Examination Plan List of Effective Pages H2 VOL2 EFFECTVE PAGES.DOC 1 of 2 Rev. 1 Volume 2 System Page Revision Distribution 1 1 List of Effective Pages 1-2 1 Table of Contents 1-2 1 Introduction 1 1 Class 1 Exam Schedule Bases 1-43 1 Class 1 Code Compliance Sheets 11 pages 1 Category B-A 1-4 1 Category B-D 1-6 1 Category B-F 1 1 Category B-G-1 1-27 1 Category B-G-2 1-7 1 Category B-J 1-30 1 Category NB-J 1-16 1 Category B-K 1-5 1 Category B-L-2 1 1 Category B-M-2 1-6 1 Category B-O 1-8 1 Class 2 Exam Schedule Bases 1-33 1 Class 2 Code Compliance Sheets 4 pages 1 Category C-A 1 1 Category C-B 1 1 Category C-C 1-17 1 Category C-F-2 1-118 1 Category C-G 1-3 1 Class 3 Exam Schedule Bases 1-4 1 Class 3 Code Compliance Sheets 1 page 1 Category D-A 1-14 1 Supports Exam Schedule Bases 1-13 1 Supports Code Compliance Sheets 1 page 1 Category F-A, Item F1.10 1-12 1 Category F-A, Item F1.10S 1-5 1 Category F-A, Item F1.20 1-33 1 Category F-A, Item F1.20S 1-11 1 Category F-A, Item F1.30 1-30 1 Category F-A, Item F1.30S 1-7 1 Category F-A, Item F1.40 1-7 1 Category F-A, Item F1.40S 1-2 1

Augmented Examinations

Hatch Unit 2 Fourth Interval Examination Plan List of Effective Pages H2 VOL2 EFFECTVE PAGES.DOC 2 of 2 Rev. 1 System Page Revision VIP-075 Basis 1-40 1 VIP-075 Compliance Sheets 1-3 1 Category OL-1 1 1 Category XB-F 1-3 1 Category XB-J 1-10 1 "Other" Augmented Examinations Bases 1-6 1 Category C-0619 1 1 Category C-0803 1-4 1 Category CF-R 1-2 1 Category FA-R 1-3 1 Category CC-R 1 1

Hatch Unit 2 Fourth Ten-Year Exam Plan TABLE OF CONTENTS H2 VOL2-T OF C.doc Page 1 of 2 Rev. 1 VOLUME 2 - Vessel and Piping Weld Information Distribution List of Effective Pages Introduction ASME Class 1 Exam Schedule Bases Class 1 Code Compliance Sheets Category B-A RPV Welds Category B-D RPV Nozzles Category B-F Dissimilar Metal Welds (See Category XB-F for >

NPS 4") Category B-G-1 Pressure Retaining Bolting > 2" Diameter Category B-G-2 Pressure Retaining Bolting < 2" Diameter Category B-J Carbon Steel Piping Welds Category NB-J Previously Exempt Piping Welds Category B-K Welded Attachments Category B-L-2 Pump Casings Category B-M-2 Valve Bodies Category B-O Welds in CRD Housings ASME Class 2 Exam Schedule Bases Class 2 Code Compliance Sheets Category C-A RHR Heat Exchanger Shell Welds Category C-B RHR Heat Exchanger Nozzle Welds Category C-C Welded Attachments Category C-F-2 Piping Welds (Includes NRC Required Thin-Wall Exams) Category C-G Pump Casing Welds ASME Class 3 Exam Schedule Bases Class 3 Code Compliance Sheets Category D-A Welded Attachments Component Support Exams Bases Class 1, 2, and 3 Component Support Code Compliance Sheets Category F-A (Item F1.10) Class 1 Piping Supports Category F-A (Item F1.10S) Class 1 Piping Snubbers Category F-A (Item F1.20) Class 2 Piping Supports Category F-A (Item F1.20S) Class 2 Piping Snubbers Category F-A (Item F1.30) Class 3 Piping Supports Category F-A (Item F1.30S) Class 3 Piping Snubbers Category F-A (Item F1.40) Class 1, 2, and 3 Equipment Supports Category F-A (Item F1.40S) Class 1, 2, and 3 Equipment Snubbers Hatch Unit 2 Fourth Ten-Year Exam Plan TABLE OF CONTENTS H2 VOL2-T OF C.doc Page 2 of 2 Rev. 1 Augmented Examinations VIP-075 Basis VIP-075 Compliance Sheets Category OL-1 Overlayed Welds Category XB-F Dissimilar Metal Welds Category XB-J Stainless Steel Welds

"Other" Augmented Examinations Bases Category C-0619 CRD/RWCU Thermal Tee Welds Selected Per NUREG-0619 Category C-803 CRD Header Welds Selected per NUREG-0803 Category CF-R RCIC Class S Welds Category FA-R RCIC Class S Supports Category CC-R RCIC Class S Welded Attachments

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN INTRODUCTION H2 Basis Doc - Introduction Page 1 of 1 Rev. 1

IWA-2420 of the 2001 Edition of Section XI with Addenda through 2003 specifies the contents of Inservice Inspection Plans and Sc hedules. HNP utilizes a two-part plan developed using industry standard Schedule Work s software to develop applicable tables.

These are:

1. The Fourth Interval Inspection Plan. This plan was developed to provide scheduling for all of the Class 1,2, and 3 components for the Fourth Interval as defined by the applicable HNP Boundary Diagrams. This document is primarily used to determine if Code scheduling requirements are being met. This plan includes:

The Fourth Interval and period dates. The Edition and Addenda that apply to the required examinations. The Code classification and identification of all components subject to examination. The identification of each of the components selected for examination and the successive exams from prior periods. The identification of drawings showing the location of items requiring examination. Code examination requirements (UT, MT, etc.) for each component selected for examination. Code Cases proposed for use and th e extent of th eir application. NRC Alternatives that change Code examination requirements.

2. Outage Plans. These plans will be developed for each outage to provide information specific to each outage. These plans include:

The listing of components selected for examination dur ing the outage. The examination procedures for each component. The description of alternative examinations and identification of components to be examined using alternative methods. The identification of calibration blocks used for ultrasonic examination of components.

Note: Schedule Works also provides a column in the Fourth Interval Inspection Plan that lists procedures to be used. This information is only need ed for outage related activities and is found in the Outage Plan. It is cons idered for information only in this plan because procedures are subject to change throughout the interval.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 1 of 43 Rev. 1 SCOPE OF EXAMINATIONS Per IWA-1400 of the Section XI Code, the Owner is responsible for determining the appropriated Code Class, for identifying the system boundaries for each class of component subject to examination, and for identifying the components exempt from examination. This requirement is met by the following:

Appropriate Code Class The determination of the appropriate Code Class for each component is made by SNC Design Organization and designated on the ISI Boundary Diagrams. These Boundary Diagrams are controlled by SNC Design Organization.

System Boundaries The system boundaries for each Code Class are designated on the ISI Boundary Diagrams.

Exempt Components The components exempt from examination are shown below in this Bases Document.

EXAMINATION REQUIREMENTS The examination requirements for the Cla ss 1 components identif ied on the Boundary Diagrams are defined in IWB-2500 for each examination category. Categories in the 2001 Edition of Section XI with Addenda through 2003 are:

Category B-A Pressure Retaining Welds in the Reactor Vessel Category B-B Vessels other than the Reactor Vessel (Not Applicable) Category B-D Full Penetration Welds of Nozzles in Vessels Category B-F Pressure Retaining Dissimilar Metal Welds Category B-G-1 Pressure Retaining Bolting Greater than 2" Diameter Category B-G-2 Pressure Retaining Bolting 2" and Less in Diameter Category B-J Pressure Retaining Welds in Piping Category B-K Valves Category B-L-1 Pressure Retaining Welds in Pump Casings (Not Applicable) Category B-L-2 Pump Casings Category B-M-1 Pressure Retaining Welds in Valve Bodies (Not Applicable) Category B-M-2 Valve Bodies Category B-N-1 Interior of Reactor Vessel (See Volume 4) Category B-N-2 Integrally Welded Core Support Structures/Interior Attachments (See Volume 4) Category B-O Pressure Retaining Welds in Control Rod Housings Category B-P Pressure Testing (See Volume 6)

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 2 of 43 Rev. 1 These examination requirements are not applicable to components exempt from examination per IWB-1220. Components exempt from examination are only subject to the pressure testing requirements. (See the Exemptions Section below for more detail).

Additionally, there are cases in which SNC deviates from the Code specified examinations; with NRC concurrence. (See the Deviations Section below for further detail). These deviations occur when:

1. Meeting the Code requirements are impractical due to configurati on, accessibility, or other factors.

2. The use of later editions or addenda of the Section XI Code, Code Cases, etc., are more appropriate or more desirable for use than the existing requirements.

EXEMPTIONS IWB-1220 defines the components that are exempt from the examination requirements of IWB-2500. Per 10 CFR 50.55a(b)(2)(xi), licensees must use IWB-1220 of the 1989 Edition of Section XI, in lieu of the 2001 Edition of Section XI with Addenda through 2003. IWB-1220(a) of the 1989 Edition states that, " components that are connected to the reactor coolant system and part of the reactor coolant pressure boundary and that of such size and shape so that upon postulated rupt ure the resulting flow of coolant from the reactor coolant system under normal plant ope rating conditions is w ithin the capacity of makeup system which are operable from on-site emergency power". In determining the size of the liquid and steam lines excluded from NDE examination, liquid lines were defined as those that penetrate the RPV below the normal water level and steam lines as

those which penetrate the RPV above the normal water level.

GE Nuclear Energy Report GE DRF Number B11-00788 was used for the 3 rd Interval exemptions and its methodology will be used for the 4 th Interval. The exception is that Condensate Make-up to the main condenser was eliminated as a make-up source because the condensate pumps are not supplied by the diesel generators. Without Condensate Make-up, the reactor coolant makeup is RCIC (360 GPM) and CRD (60 GPM) for a total of 420 GPM. The basic formula for a leak rate at 1050 psi (per GE DRF Number B11-00788) is:

Inside Diameter of a Water Line = (Square Root of the total makeup flow) 18.799 Inside Diameter of a Steam Line = 2 times the value of a water line

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 3 of 43 Rev. 1 The square root of 420 is 20.494. Therefore, for water the inside diameter exempted is 1.09" and for steam the inside diameter exempt ed is twice the value of water or 2.18". Per Piping Specification (A-21000), there are th ree Class 1 piping specifications - DBA (Schedule 160), DCA (Schedule 80) and DLA (Schedule 160). After evaluation of the inside diameter for these Piping Specifications it was determined that the following exemptions may be applied.

IWB-1220(a) EXEMPTIONS NPS 1" and smaller for Schedule 80 and Schedule 160 water lines.

NPS 2" and smaller for Schedule 80 steam lines and NPS 2.5" for Schedule 160 steam lines.

Previously, per GE DRF Number B11-00788 (including Condensate Makeup to the condenser), the exemption was 2.5" for water lines and 5.0" for steam lines. The following P&IDs were reviewed to determine if there are lines that were previously exempted but that are not exempt per the new IWA-1220(a) exemptions.

H-26000 Nuclear Boiler System Sheet 1 H-26001 Nuclear Boiler System Sheet 2 H-26003 Recirculation System Sheet 1 H-26006 CRD System Sheet 1 H-26007 CRD System Sheet 2 H-26009 Standby Liquid Control (SLC) System H-26014 RHR System Sheet 1 H-26015 RHR System Sheet 2 H-26018 Core Spray System H-26020 HPCI System Sheet 1 H-26021 HPCI System Sheet 2 H-26023 RCIC System Sheet 1 H-26024 RCIC System Sheet 2 H-26036 Reactor Water Cleanup System Sheet 1 H-26037 Reactor Water Cleanup System Sheet 2

The review indicated that the following lines needed to be added to the 4 th Interval scope:

The 2" socket-welded RPV bottom head drain to the RWCU system as shown on P&ID H-26003 (Reference isometric H-51221). These welds are shown on ISI Figure A-28A and are designate d as 2B31-1RC-2DR-1 through 50.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 4 of 43 Rev. 1 The 2" socket-welded drain line on each of the two loops as shown on P&ID H-26003. (Reference isometrics S-30804 and S-30809). These welds are shown on ISI Figure A-16A and A-18a and are designa ted as 2B31-1RC-2A-1 through 10 and 2B31-1RC-2B-1 through 12.

The 1-1/2" socket-welded SLC line as shown on P&ID H-26009 (see isometrics S-30959, S-31455, S-31489, S-31435). These welds are shown on ISI Figures A-39 through A-41 and are designated as 1C 41-1SB LC-1.5-1 through 85. The two butt welds on the safe-end are designated as 1C41-1SBLC-2-1 and 1C41-1SBLC-2-2 and are shown on Sketch 2-BE-3.

The 2N16A&B nozzles penetrate the RPV in water space. Per Sketch 2-BE-2, a dissimilar metal weld joins the 304 stainle ss steel safe-end to the Inconel nozzle. These Category B-F welds are designated as 2B11-1INST-2A-1 (2N16A) and 1B11-1INST-2B-1 (2N16B) and they are non-exempt because the ID is greater than1.09".

Per Sketch 2-BE-2, the safe-end has a socket weld end prep for a 2" pipe. While no drawings could be found for the piping, a drawing was found for the 1N11A&B nozzles which is essentially the same as the 2N16A&B nozzles. This drawing (H16964) indicates that at ther e is a 2" X 1-1/2" coupli ng welded to the safe-end.

The 1-1/2" coupling then is fu rther reduced in size by a 1-1/2" X 1" reducing insert. These socket welds are designated 2B 11-1INST-2A-2 and 3(2N16A) and 2B11-1INST-2B-2 and 3 (2N16B) and are not exempt. Per P&ID H-26001 the balance is exempt 1" DCA pipe (Sche dule 80S with a 0.957" ID ).

The 2N11A&B and 2N12A&B nozzles are the same size as the 2N16A&B nozzles; however, they penetrate the RPV near the steam separator. Invent ory lost as a result of a break in these welds would consist of steam; therefore, they are exempt since they are smaller than the IWB-1220(a) exemption for steam (2.18").

DEVIATIONS TO CLASS 1 ISI CODE REQUIREMENTS IWB-2500 provides the examination requirements for Class 1 components. As defined in Volume 1 of this ISI Plan, these Code requirements may be deviated from by:

The use of NRC approved alternatives to Code requirements per 10 CFR 50.55a(a)(3). The use of NRC approved Relief Reque sts per 10 CFR 50.55a(g)(6) when an examination requirement by the Code is determined to be impractical. The use of Code Cases approved for use by the NRC through publication in Regulatory Guide 1.147.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 5 of 43 Rev. 1 Code Case N-663 Code Case N- 663 provides that "... in lieu of the surface examination requirements for piping welds of Examination Category B- F ( NPS 4 and larger), and B- J ( NPS 4 and larger),surface examinations may be limited to areas identified by the Owner as susceptible to outside surface attack." The susceptibility criteria are listed in Table 1 of Code Case N- 663 for two types of degradation mechanisms. No Class 1 welds have been identified as being susceptible to outside surface attack. The basis is discussed below:

External (O. D.) Chloride Stress Corrosi on Cracking of Austenitic Stainless Steel For this cracking to be postulated per Code Case N-663, the:

Operating temperature must be greater than 150 0F, and the piping outside surface is within 5 pipe diameters of a probable leak, and the piping outside surface is covered with nonmetallic in sulation that is not in compliance with Regulatory Guide 1.36 or equivalent requirements.

Evaluation: All of the austenitic piping within the ISI scope is within the reactor coolant pressure boundary (RCPB). Per Section 5.2.3.3 of the FSAR, Compatibility With External Insulation and Environmental Atmosphere, the RCPB is insulated with an all-metal (stainless steel and aluminum) reflective-type insulation in compliance with Regulatory Guide 1.36 (February 1973). This type of insulation does not contain any silica, fluorides, or chlorides. It does not c ontribute to surface contamination, and it has no effect on the stainless steel components of the RCPB. Th e insulation is designed for a 40-year service life; however, this insulation is monitored so that actions are taken to provide reasonable assurance that the insulation is capable of fulfilling its intended function for 40 years and beyond.

Other Outside Surface Initiated Mechanisms Per Code Case N-663, items that are susceptible to an outside attack should be identified by a plant-specific service history review.

This review should include plant-specific processes and programs that minimize chlorides and other contaminants.

Evaluation: Due to ID initiated IGSCC, numerous examinations of the austenitic welds and adjacent base material has been performed over the past 15+ years and no evidence of OD initiated stress corrosion cracking has been observed. (Note: All of the stainless

steel piping was replaced to the extent practical with 316NG which is relatively immune to stress corrosion cracking). Additionally, ISI personnel associated with Hatch over the past 20 years have no knowledge of OD originated cracking in au stenitic piping 4" diameter and over. (There has been OD originated cracking in some socket welds due to

fatigue, but socket weld are not covered by Code Case N-663). Plant-specific processes and programs that minimize chlorides and other contaminants are:

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 6 of 43 Rev. 1 The SNC purchase specification for thermal Insulation for stainless steel, require insulation suppliers to provide material that meets the criteria of Regulatory Guide 1.36. Each Purchase Order imposes Reg. Guide 1.36 and ANSI N45.2 covering leach able properties and their acceptable levels for contact with Stainless Steel.

The SNC Chemical Product Control Program provides procedure guidance for control of contaminants from chemical products to be used on site. Reference Hatch procedure 60 AC HPX-008-0 E.

I. Hatch Chemical Control.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 7 of 43 Rev. 1 ISI PLAN TABLES The ISI Plan Tables are generated by the industry standard ScheduleWorks ISI software using a standard format. It should be noted th at the Scope/Method/Procedure field is for information only. This information may be changed during an outage by authorized IDDEAL software `users at the site, but it will not be reflected in the ISI Plan until the plan is updated after the outage. When using these tables the user needs to understand the following symbols:

Scheduled "s" To schedule a component, place the identifier "s" in the required period/outage.

Completed "c" Upon exam completion for a scheduled component and by uploading the outage scope from IDDEAL back to ScheduleWorks, an "s" will be updated to completed "c".

Re-scheduled "r" Once a component has been scheduled, and you wish to reschedule to another outage, replace the scheduled "s" with a rescheduled "r" and enter an "s" in the new outage schedule. Expanded Scope "e" To increase a work scope without taking code credit in the percentage calculations, enter an expanded "e".

Expanded Scope Completed "E" Upon exam completion of an expanded scope and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "E" the exam scope is completed. Additional Scheduled "a" After an initial expanded work scope has been identified and you wish to add an increased expanded work scope, enter an additional expanded scope "a". Additional Completed "A" Upon exam completion of an additional expanded scope and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "A" the exam scope is completed.

Partial "p" To track partially completed component examination requirements enter a partial "p". Deferred "d" Once a component has been scheduled, and you wish to defer the inspection to another Outage, or Period, replace the scheduled "s" with a deferred "d" and enter an "s" in the new Outage. Limited "l" To track limited component examinations or limited completions of requirements enter "l". Multiple Scheduled "b For multiple scheduling of the same component in successive Outages or Period s within an Interval enter "b". Multiple Completed "B" Upon exam completion of a multiple scope in the same Interval and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "B" the exam scope is completed. This multiple scheduling scope will not count as completed for code calculations.

Tickler "t" To track exam scopes or use as reminder or identifier to confirm scheduling enter "t". Successive Exams "h" Successive examinations. Successive Exams Completed "H" Upon exam completion of a successive scope and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "H" the exam scope is completed.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 8 of 43 Rev. 1 Category B-A - Class 1 RPV Item B1.11 and B1.12 Shell Welds Configuration The HNP-2 RPV shell has four Item B1.11 Circumferential welds - 2C-2, 2C-3, 2C-4, and 2C-5 and twelve Item B1.12 longitudina l welds - 2C-1-A, 2C-1-B, 2C-1-C, 2C-2-A, 2C-2-B, 2C-2-1C, 2C-3-A, 2C-3-B, 2C 1C, 2C-4-A, 2C-4-B, and 2C-4-C.

1 st Interval Examinations The 1 st Interval began on 9/5/79; however, HNP-2 was early updated effective 12/31/85 prior to the examination of the shell welds. This update changed the HNP-2 interval and period dates so that they coincided with the interval and period dates for HNP-1. At the time of the update, the remaining examinations in the original 1 st interval (all B1.11 and B1.12 exams) were required to be performed during the 1 st period of the new 2 nd interval (essentially where they had been originally scheduled).

These examinations were performed in Winter 1988 during the 1 st Period of the 2 nd Interval, as required. The scope was determined using the 1974 Code/Summer 1975 requirements, which was 5% of each circumferential weld and 10% of each longitudinal weld. Examinations were performed by SWRI to the 1980 Code requirements using mechanized equipment. These examinations completed the 1 st Interval requirements.

2 nd Interval Examinations 1 st Interval examinations were performed in 1988; therefore, 2 nd Interval examinations were due by the 1998 outage. However, 10 CFR 50.55a(g)(6)(ii)(A) was issued by the NRC to require all licensees to augment their RPV examination by implementing once, as part of the inservice inspection interval in effect on September 8, 1992, the examination requirements for reactor vessel shell welds specified in Item B1.10 of Examination Category B - A, "Pressure Retaining Welds in Reactor Vessel," in Table IWB - 2500 - 1 of subsection IWB of the 1989 Edition of section XI, Division 1, of the ASME Boiler and Pressure Vessel Code.

GPC evaluated whether to perform these examinations from the ID or the OD of the RPV and it was determined that the OD examinations had significantly more coverage. These OD examinations were performed during the Fall 1995 refueling outage. All welds had greater than 90% coverage, except for Weld 2C-2. GPC letter HL-5250 dated October 29, 1996 requested relief for the limited examination coverage of weld 2C-2, which had only 83.7% coverage due to stabilizer brack ets being welded dire ctly onto 2C-2.

Approval was granted by the NRC Safety Evaluation dated February 21, 1997. These examinations completed the augmented examination requirements and the 2 nd Interval examination requirements.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 9 of 43 Rev. 1 3rd Interval Examinations Since 2 nd Interval examinations were performed in the Fall 1995 during the last outage of the 2 nd 10-year Interval, the next examinations are due at the end of the 3 rd Interval.

HNP-2 changed to a 24 month operating cycl e beginning after the February 2003 outage and the next outages are scheduled for Febr uary 2005 and February 2007. The February 2007 outage is 14 months past the end of the interval and cannot be used for 3 rd Interval activities; therefore, the examinations were schedule d during the February 2005 outage.

Per Table IWB-2500-1, Category B-A of the 1989 Code all of the circumferential welds and the longitudinal welds require a volumetric examination. However, to support shorter outage windows, relief (see RR-38) ha s been requested, base d on the technical basis provided in BWRVIP-05, to allow the volumetric exam ination of the four Item B1.11 circumferential welds to be deleted.

RR-38 granted by NRC SE dated 1/28/05.

The twelve longitudinal weld examinations were examined in February 2005 (2R18) using the 1989 Edition of Section XI.

4 th Interval Examinations The twelve longitudinal weld examinations will be scheduled for examination in February 2015 (2R23). Relief will be required using BWRVIP-05 to allow the deletion of the volumetric examination of the four Item B1.11 circumferential welds.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 10 of 43 Rev. 1 Category B-A - Class 1 RPV Item B1.21 Bottom Head Circumferential Weld Configuration There is one circumferential weld located on the bottom head. Circumferential weld 2C-7 connects the dome to the torus. It is located inside the support skirt.

First and Second Interval Examinations HNP-2 was "early" updated effective January 1, 1986. This update changed the HNP-2 Code, interval dates, and period dates so that they coincided with HNP-1. (Therefore, the 3 rd Period of the 1 st Interval for HNP-2 became the 1 st Period of the 2 nd Interval). Per Relief Request 2.1 (submitted in the 2 nd Interval Program) the required 1 st Interval examinations were to be completed for 2C-7 (approximately 5% of the length per the 1974/Summer 1975 Code) in the 1 st Period of the 2 nd Interval. Additionally, weld 2C-7 was required to be "100%" examined during the 2 nd Interval to meet the 1980 Code requirements. Examinations were performed as follows:

Per Note 2 in the 2 nd Interval ISI Plan, 2C-7 was examined in 1986 to meet the 5% requirement of the 1974 Code. From the data sheet, the weld was examined in excess of 5%, but the exact amount of coverage was indeterminate. This examination satisfied the 1 st Interval requirements.

Weld 2C-7 was re-examined during the Fall 1995 outage (3 rd Period of the 2 nd Interval) using GERIS to meet the 2 nd Interval requirements using the 1980 Code with Addenda through Winter 1981. Ninety-three non-geometric indications were evaluated and found acceptable. Code coverage was in excess of 95%. This examination satisfied the 2 nd Interval requirements.

Third Interval Examinations Scope: 2C-7

Since the 2 nd Interval examination of 2C-7 was performed during 1995, the 3 rd Interval examination of 2C-7 was performed in February 2005 (2R18) using the 1989 Code.

4th Interval Examinations Scope: 2C-7

Since the 3rd Interval examination of 2C-7 was performed during 2005, the 4 th Interval examination of 2C-7 will be scheduled for February 2015 (2R23).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 11 of 43 Rev. 1 Category B-A - Class 1 RPV Item B1.22 Bottom Head Meridional Welds Configuration The HNP-2 bottom head consists of a 4-piece dome welded together with four meridional welds 2BHD-A thru D and a 7-piece torus welded together with seven meridional welds 2BHT-A thru G. (There is a support sk irt welded to the bottom head between circumferential welds 2C-7 and 2C-5 that covers a portion of each meridional torus weld). First and Second Interval Examinations HNP-2 was "early" updated effective January 1, 1986. This update changed the HNP-2 Code, interval dates, and period dates so that they coincided with HNP-1. (Therefore, the 3 rd Period of the 1 st Interval for HNP-2 became the 1 st Period of the 2 nd Interval). Per Relief Request 2.1 (submitted in the 2 nd Interval Program) original 1 st Interval examinations were to be completed for the eleven meridional welds (approximately 10% of the length of each of the eleven we lds per the 1974/Summer 1975 Code) during the same time frame they were origin ally scheduled (originally the 3 rd Period of the 1 st Interval which changed to the 1 st Period of the 2 nd Interval). Add itionally, one of the seven bottom head torus meridional weld was required to be "100%" examined, to the extent practical, during the 2 nd Interval per th e 1980 Code.

Per information supplied in Note 3 of the 2 nd Interval ISI Plan and as shown on the applicable data sheets:

Each of the four dome meridional welds was examined in Fall 1986 (1 st Period of the 2 nd Interval) to the extent pr actical (28.5" to 30"). The dome meridional welds were estimated to be approximately 60" long, with about half of each weld inaccessible due to the control rod drive penetrations.

Each of the seven torus meridional welds was examined in Fall 1986 (1 st Period of the 2 nd Interval) to the extent practical (30"). Limitations existed due to the RPV skirt weld. More than 10% of each of the eleven meridional welds was examined; therefore, the original 1 st Interval 1974 Section XI requirements were satisfied. Additionally, since each meridional weld had been examined to the extent practical, the 2 nd Interval requirement per the 1980 Code to examine one meridional weld, to the extent practical, was also satisfied.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 12 of 43 Rev. 1 Third Interval Examinations Since the 2 nd Interval examinations were completed in Fall 1986 (1 st Period of the 2 nd Interval), the 3 rd Interval examinations were co mpleted during the 2R13 Spring 1997 outage (1 st Period of the 3 rd Interval) per the requireme nts of the 1989 Code. The 1989 Code required that the accessible length of all the meridional welds be examined. Examinations were pre-Appendix VIII and had the following limitations:

2BHD-A, B, C, D Manual examinations limited to 31" of each of the four welds. Limitations were due to CRD interference.

2BHT-A, B, C, D, E, F, G GERIS automated scans (GE procedure UT-HAT-702V0, Rev. 3) were used to examine 38" of each weld. Supplemental manual scans were performed on 11" yielding a total of 49" of each weld being examined.

Composite coverage was 88.7%. Limitations were due to the skirt weld.

Upjohn Welds GE SIL 651 was subsequently issued on Augus t 7, 2003, to notify the industry of flaws detected during Appendix VIII qualified ISI examinations at Fermi in RPV seams that were welded using the upjohn welding process. Pre-Appendix VIII UT examinations at Fermi did not report these flaws; however, review of the previous examination results showed that indications were present in the earlier data and were the same size as reported for the Appendix VIII examinations. GE indicated that these flaws were not reported in previous examinations because the indication did not require recording under the pre-Appendix VIII rules. Subsequent implementation of Appendix VIII has increased the sensitivity of ISI techniques and has resulted in more stringent data recording requirements.

Due to the CE work load during fabrication, there were times when all of the head positioners were in use and an "upjohn weld" process was used. Torus head segment

plates were placed vertically on the floor end-to-end and a manual stick weld process was used. Welding started at the floor and the stringers were run from the plate ID to the plate OD in a horizontal position. After the first layer was made, subsequent layers would be added, continuing until the top of the plate was reached. The issue with this type of weld was that during the radiograph pr ocess, indications such as slag or cracks could have been missed, because only the end of the indication would be seen.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 13 of 43 Rev. 1 Per Volume 2, Section 10., page 3 of the GE prepared HNP-2 RPV Examination Plan, all weld seams welded to procedure MA-500-0 and MA-509-0 were welded using the Upjohn process. This included:

Unit 2 lower dome weld seams 2BHD-A thru D Unit 2 lower head torus weld seams 2BHT-A thru G The lower dome weld seams and the lower head torus weld seams were examined during 2R13. These examinations were all pre-A ppendix VIII. Because the top head is examined on the refueling floor it was determined that during next Appendix VIII examinations, if there were indications, the dose would be low while resolving the indications. However, because of dose issues associated with resolving potential indications when performing Appendix VIII examination on the lower head welds, it was determined that they would be re-examined during 2R18 (while automated GERIS equipment was onsite for the RPV examinations).

The rationale was that if a significant number of indications were found during the manual examinations, the automated GERIS equipment (which is to be onsite during the RPV examinations) could be used to better characterize the indications.

Manual type Appendix VIII qualified examinations were performed on each of the lower dome and lower head welds, to the extent practical, in February 2005 (2R18) using the 1989 Code. No reportable indications were detected.

4 th Interval Examinations Since the 3 rd Interval examinations were complete ly redone in February 2005 (2R18) per Appendix VIII requirements, the 4 th Interval examination will be scheduled for February 2015 (2R23).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 14 of 43 Rev. 1 Category B-A - Class 1 RPV Item B1.21 Closure Head Circumferential Weld Configuration The HNP-2 closure head has one B1.21 "dollar plate" circumferential weld (2HC-1).

First Interval Examinations 5% of the 2HC-1 was examined in Spring 1985 to meet the 1974 Section XI Code with Summer 1975 addenda requirements. This examination was prior to the "early update" and it completed the 1 st Interval requirements.

Second Interval Examinations The weld was examined in 1992 to the extent practical per the 1980 Edition of Section XI. Coverage was 97% with limitations due to the lifting lugs. This examination satisfied the 2 nd Interval requirements.

Third Interval Examinations Scope: 2HC-1 The 2 nd Interval examinations were performed during the Spring 1992 outage (2nd Period of the 2 nd Interval). For the 3 rd Interval, the volumetric examination of 2HC-1 was examined in February 2005 (3 rd Period of the 3 rd Interval). Outside of the nominal successive inspection requirements of IWB-2420(a). No reportable indications were detected during the examination; therefore, th e structural integrity of the weld was and continues to be assured.

4th Interval Examinations Scope: 2HC-1

Since the 3rd Interval examination was performed during 2005, the 4 th Interval examination of will be scheduled for February 2015 (2R23).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 15 of 43 Rev. 1 Category B-A - Class 1 RPV Item B 1.22 Closure Head Meridional Welds Configuration The HNP-2 closure head has eight B1.22 meridional welds (HC-1-A, HC-1-B, HC-1-C, HC-1-D, HC-1-E, HC-1-F, HC-1-G, and HC-1-H).

First Interval Examinations Four of the welds - 2HC-1-A, 2HC-1-C, 2HC-1-E, and 2HC-1-G - were examined in 1985 (2 nd Period of the 1 st Interval) to the requirements of the1974 Edition of Section XI (with Addenda through Summer 1975) prior to the "early" Code update. Only 10% of each weld was required to be examined.

After the 1985 outage, HNP-2 was "early" updated effective January 1, 1986. This update changed the HNP-2 Code, interval dates, and period dates so that they coincided with HNP-1. (Therefore, the 3 rd Period of the 1 st Interval for HNP-2 became the 1 st Period of the 2 nd Interval). Per Relief Request 2.1 (submitted in the 2 nd Interval Program) the remaining four 1 st Interval examinations would be need to be completed to meet the 1974 Code requirements (approximately 10% of the length of each of the four welds per the 1974/Summer 1975 Code). In 1986 (new 2 nd Interval, 1 st Period) at least 10% of the length of the four remaining meridional we lds (2HC-1-B, 2HC-1-D, 2HC-1-F, and 2HC-1-H) was examined. These examinations combined with the 1985 examinations completed the original 1 st Interval examination requirements.

Second Interval Examinations Weld 2HC-1-A was "100%" examined in Spring 1991 to meet the 2 nd Interval 1980 Code requirements. This examination satisfied the 2 nd Interval Code requirements.

Third Interval Examinations Per Volume 2, Section 10, page 3 of the GE prepared HNP-2 RPV Examination Plan, all weld seams welded to procedure MA-500-0 and MA-509-0 were welded using the Upjohn process. This included the top head meridional weld seams 2HC-1-A thru H.

The 1989 Code required that each weld be 100% examined to the extent practical. Welds 2HC-1-B, D, F, and H were examined during 2R13 and welds 2HC-1-A, C, E, and G were examined during 2R14. All of these examinations were pre-Appendix VIII; however, even though they are Upjohn welds, re-examination was not performed because there is not a dose issue associated with the potential evaluation of indications (as compared to the bottom head). Note: Since weld 2HC-1-A was the only weld examined during the 2 nd interval, the successive examination requirements of IWB-2420(a) were not applicable for 3 rd Interval scheduling purposes.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 16 of 43 Rev. 1 4 th Interval Examinations Welds 2HC-1-B, D, F, and H were examined during Period 1 and welds 2HC-1-A, C, E, and G were examined during Period 2. Table IWB-2500-1, Category B-A allows the deferral of these examinations; as a result, all welds will be examined during the 1 st Period (2HC-1-A, C, E, and G will be examined about 3 years early).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 17 of 43 Rev. 1 Category B-A - Class 1 Item B1.30 RPV Shell To Flange Weld Configuration There is one RPV shell-to-flange weld (2C-1).

First Interval Examinations Segments of the weld were examined in 1982, 1985, and 1986 to meet the 1 st interval 1974 Code requirements to examine the complete length of the weld.

Second Interval Examinations Segments of the weld were examined in 1991 and in 1994. Then, the entire length of the weld was examined in 1995 (3 rd Period of 2 nd Interval) using GERIS automated exams from the shell side (44.7% coverage) and manual supplemental exams (67.9% coverage) from the flange surface. This examination completed the 2 nd Interval requirements and "re-zeroed" the examination, so that in fu ture intervals 100% of the length could be examined at one time.

Third Interval Examinations Scope: 2C-1

Per Table IWB-2500-1, Category B-A of the 1989 Code the entire length of this weld is required to be volumetrically examined.

100% of the weld was examined during 2R18 (2/2005) which is the last outage of the 3 rd Interval.

4 th Interval Examinations Scope: 2C-1

Per Table IWB-2500-1, Category B-A of the 2003 A ddenda the entire length of this weld is required to be volumetrically examined.

100% of the weld was examined during 2R18 (2/2005) and it will be re-examined during 2R23 (2/2015).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 18 of 43 Rev. 1 Category B-A - Class 1 Item B1.40 RP V Closure Head to Flange Weld Configuration There is one RPV closure head-to-flange weld (2HC-2).

First Interval Examinations Examined 66% of the weld in 1985 prior to the "early" update; however, because of a reportable indication (See INF S85H2I003) the remaining 1/3 rd was examined. This completed the first interval requirements.

Second Interval Examinations The 1/3 rd of the weld containing the indications detected during the 1985 examination was re-examined in 1986, 1988, and 1989. Examinations were performed in Fall 1992 and Fall 1995 to complete the 2 nd Interval requirements of the 1980 Code.

Third Interval Examinations Per Table IWB-2500-1, Category B-A of the 1989 Code the entire length of this weld is required to be volumetrically examined.

100% of the length of the weld was examined in the 1 st Period of the 3 rd Interval 2R13 (Spring 1997) to satisfy the 3 rd Interval 1989 Code requirements. This examination completed the 3 rd Interval requirements and "re-zeroed" the examination, such that, 100% of the weld length could be examined at one time, during future examinations.

4 th Interval Examinations Per Table IWB-2500-1, Category B-A of the 2003 A ddenda the entire length of this weld is required to be volumetrically examined.

100% of the weld was examined during 2R13 (Spring 1997) and it will be re-examined during 2R19 (2/2007).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 19 of 43 Rev. 1 Category B-D - Class 1 Item B3.90 Full-Penetration Welds of Nozzles in Vessels Configuration The only Class 1 vessel at HNP is the reactor pressure vess el (RPV). There are 29 RPV nozzles installed on the RPV using full-penetration welds. Nozzle 2N15 (bottom head drain) is completely inaccessible due to the proximity of the CRDs. Relief similar to that submitted in the 3 rd Interval via RR-3 will be needed.

First Interval Examinations Examinations were performed on the nozzles 2N1A&B, 2N2C, E, F, H, &J, 2N3A, B, &D, 2N4C&D, 2N5A, 2N6A, 2N7, and 2N9 as shown in the 1 st Interval column in Table 1-1. However, as discussed in the Introduction (effective December 31, 1985) the HNP-2 Code, interval dates, and period dates were upda ted so that they coincided with HNP-1. The remaining 1 st Interval nozzle examinations (nozzles 2N2A, 2N2B, 2N2D, 2N2G, 2N2K, 2N3C, 2N4A, 2N4B, 2N 5B, 2N6B, 2N8A, and 2N8B) were examined from 1986 through 1989 during the 1 st Period of the 2 nd Interval (originally the 3 rd Period of the 1 st Interval). These examinations completed the 1 st Interval requirements.

Second Interval Examinations The new 2 nd Interval was scheduled from 1/1/86 through 12/31/95 to coincide with HNP-1. (Note: Prior to the early update the 2 nd Interval for HNP-2 was scheduled from 9/5/89 through 9/5/99).

As shown in Table 1-1, 2 nd Interval examinations were performed from 1988 through 1994 for nozzles 2N1A, 2N1B, 2N2B, 2N2C, 2N2E, 2N2F, 2N2H, 2N2J, 2N3A, 2N3B, 2N3C, 2N3D, 2N4A, 2N4B , 2N4C, 2N4D, 2N5A, 2N6A, 2N6B, 2N7, and 2N9.

Second Interval examinations were also performed in 1997 for 2N2A, 2N2D, 2N2G, 2N2K, 2N8A, and 2N8B. While the 1997 outage wa s designated as the first outage in the new 3 rd Interval, before the early update, this outage would have occurred during the 2 nd Interval. Additionally, the 1 st interval examination of thes e nozzles had been performed about 9 to 10+ years earlier. Therefore, the examination of these six nozzles in 1997 was appropriate.

The 2 nd Interval examination of 2N5B was not performed until the Spring 2000 outage. While this outage was designated as the first outage of the new 2 nd Period of the 3 rd Interval, before the early upda te, this outage would have o ccurred about 6 months past the end of the 2 nd Interval (the old 2 nd Interval would have ended on 9/4/99) which was acceptable per IWB-2412. Additionally, the 1 st interval examination of these nozzles had been performed about 10+ years earlier. Therefore, the examination of this nozzle in 2000 was acceptable. These examinations closed out the 2 nd Interval requirements.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 20 of 43 Rev. 1 Third Interval Examinations Per Table IWB-2500-1, Category B-D of th e 1989 Code 100% of these welds are required to be volumetrically examined.

As discussed above, because of the early update, some 1 st Interval examinations were performed in the new 2nd Interval and some 2 nd Interval examinations were performed in the new 3 rd Interval. This approach, while tec hnically sound, leads to difficulties in reporting (e.g., was the examination a 1 st Interval examination or was it a 2 nd Interval examination). Therefore, a philosophical change was made for the 3 rd Interval such that all of the 3 rd Interval examinations would be completed by the end of the new 3 rd Interval.

This change required that if a 2 nd Interval examination was performed in the 1 st or 2 nd Period of the new 3 rd Interval, that the weld would be re-examined in the 3 rd Period for 3 rd Interval credit. There were seven cases where welds were examined for 2 nd Interval credit in the new 3 rd Interval and then re-examined for 3 rd Interval credit. Note: In several cases, additional welds were re-examined to esta blish a pattern for the 4 th Interval such that automated equipment woul d only be needed during two outages.

This change is technically appropriate because the Section XI Code intent is to perform an examination of each nozzle in the 1 st interval and then to re-examine each nozzle about every 10 years. As shown in Table 1-1 the philosophy of examining each weld every 10 years is maintained.

Table IWB-2500-1 of the 1989 Code requires that the Category B-D examinations be spread out during the 3rd interval such th at 25% to 50% of the examinations are performed by the end of the 1 st Period and the remainder by the end of the 3 rd Interval. This requirement was not specifically met for the examinations being credited for the 3 rd Interval because per Table 1-1 only six welds were examined for 3 rd Interval Code credit during the 1 st Period, while at least seven would have been required. However, eleven total examinations (39% of the welds) were actually performed during the 1 st Period of the 3 rd Interval. It is believed that these percentages are consistent with the intent of the Table IWB-2500-1 requirement to examine 25% to 50% of the nozzle welds in the 1 st period and to then examine the rema inder by the end of the interval.

4 th Interval Examinations Examinations are required per the 2001 Ed ition of Section XI with Addenda through 2003. (Deferral of the examinations until the end of the Interval is not permitted because the deferral is for PWRs). Per Footnote 2 of Table IWB-2500-1, Category B-D, at least 25% but not more than 50% (credited) of the nozzle examinations shall be completed by the end of the first inspec tion period, and the remainder by the end of the inspection interval. Thirty-three percent of the examinations are scheduled in the 1 st Period with the balance scheduled throughout the remainder of the 4 th interval. Relief will be required for the 2N15 nozzle due to inaccessibility. (See Table 1-1).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 21 of 43 Rev. 1 TABLE 1-1 CATEGORY B-D, ITEM B 3.90 INTERVAL NOZZLE- DESCRIPTION 1 ST 2 ND 3 RD 4th P1 P2 P3 P1 P2 P3 2N1A-RC Out F80 S91 S00 2R20(2/09) 2N1B-RC Out S85 S94 S05 2R23 (2/15) 2N2A-RC Inlet W88 S97 S05 2R23 (2/15) 2N2B-RC Inlet F89,S94 S05 2R23 (2/15) 2N2C-RC Inlet S85 92 S00 2R20 (2/09) 2N2D-RC Inlet W88 S97 S05 2R23 (2/15) 2N2E-RC Inlet S82 S91 S00 2R20 (2/09) 2N2F-RC Inlet S85 S94 S05 2R23 (2/15) 2N2G-RC Inlet W88 S97 S05 2R23 (2/15) 2N2H-RC Inlet F80 S91 S00 2R20 (2/09) 2N2J-RC Inlet S85 S94 S05 2R23 (2/15) 2N2K-RC Inlet W88 S97 S05 2R23 (2/15) 2N3A-MS S82 S91 S97 S05 2R23 (2/15) 2N3B-MS S85 S94 S97 S05 2R23 (2/15) 2N3C-MS F89,92 S00 2R20 (2/09) 2N3D-MS S80 S91 S00 2R20 (2/09) 2N4A FW F86,S94 S97 S05 2R23 (2/15) 2N4B FW F86,S94 S97 S05 2R23 (2/15) 2N4C FW S84 S94 S05 2R23 (2/15) 2N4D FW F80 W88,S91 S94 S05 2R23 (2/15) 2N5A-CS S85 S94 S05 2R23 (2/15) 2N5B-CS F89 S00 S05 2R23 (2/15) 2N6A-Spray 82 S91 S00 2R20 (2/09) 2N6B-Spray 89 92 S00 2R20 (2/09) 2N7-Vent 82 S91 S00 2R20 (2/09) 2N8A-JP Instr F86 S97 S05 2R23 (2/15) 2N8B-JP Instr F86 S97 S05 2R23 (2/15) 2N9 CRD F80 S91 S97 S05 2R23 (2/15) 2N15 Drain (1) (1) (1) (1) 1 st Interval Credit 2 nd Interval Credit 3rd Interval Credit Re-zero exams Notes: 1. The 2N15 RPV drain nozzle is inaccessible because it is located in the center of the bottom head and is surrounded by the CRDs. The SE for RR-3 granted 3 rd interval approval to not perform the required examinations. Similar approval will be required for the 4 th Interval.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 22 of 43 Rev. 1 Category B-D - Class 1 Item B 3.100 - Inside Radius Area in Nozzles Welded to Vessels Using Full-Penetration Welds Configuration The only Class 1 vessel at HNP is the reactor pressure vess el (RPV). There are 29 RPV nozzles installed on the RPV using full-penetration welds. Nozzle 2N15 (bottom head drain) is completely inaccessible due to the proximity of the CRDs. (See RR-3).

First Interval Examinations As shown in Table 1-2, 1 st Interval examinations were performed from 1980 through 1985 for the nozzle inner radii for nozzles 2N1A, 2N1B, 2N2B, 2N2C, 2N2E, 2N2F, 2N2H, 2N2J, 2N3A, 2N3B, 2N3D, 2N4A, 2N4B, 2N4C, 2N4D, 2N5A, 2N6A, 2N7, 2N8A and 2N9.

Effective December 31, 1985 the HNP-2 Code, interval dates, and period dates were updated so that they coincided with HNP-1. Examinations were subsequently performed on nozzles 2N2A, 2N2D, 2N2G, 2N2K, 2N3C, 2N5B, 2N6B, and 2N8B from 1986 through 1989 during the 1 st Period of the 2 nd Interval (originally the 3 rd Period of the 1 st Interval). These examinations completed the 1 st Interval requirements.

Note: Examination of the 2N4A-D Feedwater nozzle inner ra dius and bore were performed numerous times to meet NUREG-0619 requirements. Only one examination per nozzle was credited for Code purposes. See Feedwater Nozzles in the Augmented Section for additional information.

Second Interval Examinations The new 2 nd Interval was scheduled from 1/1/86 through 12/31/95 to coincide with HNP-

1. (Prior to the earl y update, the HNP-2 2 nd Interval was scheduled from 9/5/89 through 9/5/99). As shown in Table 1-2, 2 nd Interval examinations were performed from 1989 through 1994 for nozzles 2N1A, 2N1B, 2N2B, 2N2C, 2N2E, 2N2F, 2N2H, 2N2J, 2N3A, 2N3B, 2N3C, 2N3D, 2N4A, 2N4B, 2N 4C, 2N4D, 2N5A, 2N6A, 2N 6B, 2N7, 2N8A, and 2N9. Second Interval examinations were also performed in 1997 for 2N2A, 2N2D, 2N2G, 2N2K, and 2N8B. While the 1997 outage was de signated as the first outage in the 3 rd Interval, before the early update this outage would have occurred during the 2 nd Interval. Additionally, the 1 st interval examination of these nozzles had been performed about 9 to 10 years earlier or less. Therefore, the examination of these six nozzles in 1997 was appropriate.

The 2 nd Interval examination of 2N5B was not performed until the Spring 2000 outage. While this outage was designated as the first outage of the new 2 nd Period of the 3 rd Interval, before the early upda te, this outage would have oc curred about 6 months past HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 23 of 43 Rev. 1 the end of the 2 nd Interval (the old 2 nd Interval would have ended on 9/4/99) which was acceptable per IWB-2412. Additionally, the 1 st interval examination of these nozzles had been performed about 10+ years earlier. Therefore, the examination of this nozzle in 2000 was acceptable. These examinations closed out the 2 nd Interval requirements.

Note: Examination of the 2N4A-D Feedwater nozzle inner ra dius and bore were performed numerous times to meet NUREG-0619 requirements. Only one examination per each nozzle was credited for Code examination purposes. See Revised Feedwater

Nozzle Inner Radius Inspection Criteria in this document for further information on these examinations.

Third Interval Examinations Per Table IWB-2500-1, Category B-D of the 1989 Code 100% of the nozzles must have their inner radius volumetrically examined.

NOTE Beginning in 2000, Relief Request RR-34, Revision 2 was used to perform an enhanced visual examina tion of the nozzle inner radius in lieu of the required volumetric examination of closure head nozzles 2N6A&B, 2N7, and 2N9 in lieu of the required volumetric examination.

It could have also been used fo r RPV nozzles 2N1A&B and 2N3A-D, but was not.

Relief Request RR-37, Revision 1 may have been used to perform an enhanced visual examination of the nozzle inner radius in lieu of the required volumetric examination fo r RPV nozzles 2N2A-H, 2N2J&K, 2N5A&B, and 2N8A&B. It was not used.

As discussed above, because of the early update, some 1 st Interval examinations were performed in the new 2nd Interval and some 2 nd Interval examinations were performed in the new 3 rd Interval. This approach, while tec hnically sound, leads to difficulties in reporting (e.g., was the examination a 1 st Interval examination or was it a 2 nd Interval examination?). Therefore, a philosophical change was made for the 3 rd Interval such that all of the 3 rd Interval examinations would be completed by the end of the new 3 rd Interval.

This change required that if a 2 nd Interval examination was performed in the 1 st or 2 nd Period of the new 3 rd Interval, that the weld would be re-examined in the 3 rd Period for 3 rd Interval credit. There were six cases where the nozzle inner radius was examined for 2 nd Interval credit in the new 3 rd Interval and then re-examined for 3 rd Interval credit. Note: In several cases, additional nozzle inner radii were re-examined to establish a pattern for the 4 th Interval such that automated equipmen t would only be needed during two outages.

This change is technically appropriate because the Section XI Code intent is to perform an examination of each nozzle in the 1 st interval and then to re-examine each nozzle HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 24 of 43 Rev. 1 about every 10 years. As shown in Table 1-2 the philosophy of examining each nozzle inner radius every 10 years is maintained.

Table IWB-2500-1 of the 1989 Code requires that the Category B-D examinations be spread out during the 3rd interval such th at 25% to 50% of the examinations are performed by the end of the 1 st Period and the remainder by the end of the 3 rd Interval. This requirement was not specifically met for the exams being credited for the 3 rd Interval because per Table 1-2 only six nozzle inner radii were examined for 3 rd Interval Code credit during the 1 st Period, while at least seven would have been required. However, eleven total examinations (43% of the total welds) were actually performed during the 1 st Period of the 3 rd Interval. It is believed that thes e percentages are consistent with the intent of the Table IWB-2500-1 requirement to examine 25% to 50% of the nozzle inner radii in the 1 st period and to then examine the remainder by the end of the interval.

Examinations of the 2N4A-D Feedwater nozzle inner radius and bore were performed once during the 10-year interval to meet "Alternate BWR Feedwater Nozzle Inspection Requirements". See Revised Feedwater Nozzle Inner Radius Inspection Criteria in this document.

4 th Interval Examinations Examinations are required per the 2001 Ed ition of Section XI with Addenda through 2003. (Deferral of the examinations until the end of the Interval is not permitted because the deferral is for PWRs). Per Footnote 2 of Table IWB-2500-1, Category B-D, at least 25% but not more than 50% (credited) of the nozzle examinations shall be completed by the end of the first inspec tion period, and the remainder by the end of the inspection interval. Thirty-three percent of the examinations are scheduled in the 1 st Period with the balance scheduled throughout the remainder of the 4 th interval. Relief will be required for the 2N15 nozzle due to inaccessibility. (See Table 1-2).

In place of a UT examination, SNC may perform a visual examination of the RPV nozzles (except for the Feedwater Nozzles) per Code Case N648-1, with enhanced magnification that has a resolution sensitivity to detect a 1-mil width wire or crack, utilizing the allowable flaw length criteria of Table IWB-3512-1 with limiting assumptions on the flaw aspect ratio. The provisions of Table IWB-2500-1, Examination Category B-D, continue to apply except that, in place of examination volumes, the surfaces to be examined are the external surfaces shown in the figures applicable to this table.

Note: Per NUREG-0619 augmented examinati ons of the feedwater nozzle inner radius (and bore) for a welded in thermal sleeve configuration are required every 2 nd refueling outage. However, due to improved automated UT examination technology and lack of cracking in the newer thermal sleeve conf igurations, the frequency is now Code frequency (see "Feedwater Nozzle Augmented Requirements" later in this document for detailed discussion).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 25 of 43 Rev. 1 TABLE 1-2 CATEGORY B-D, ITEM B 3.100 INTERVAL NOZZLE- DESCRIPTION 1 ST 2 ND 3 RD 4th P1 P2 P3 P1 P2 P3 2N1A-RC Out F80 89 S00 2R20(2/09) 2N1B-RC Out S85 S94 S05 2R23 (2/15) 2N2A-RC Inlet W88 S97 S05 2R23 (2/15) 2N2B-RC Inlet F80 S94 S05 2R23 (2/15) 2N2C-RC Inlet S85 92 S00 2R20 (2/09) 2N2D-RC Inlet W88 S97 S05 2R23 (2/15) 2N2E-RC Inlet S82 S91 S00 2R20 (2/09) 2N2F-RC Inlet S85 S94 S05 2R23 (2/15) 2N2G-RC Inlet W88 S97 S05 2R23 (2/15) 2N2H-RC Inlet F80 S91 S00 2R20 (2/09) 2N2J-RC Inlet S85 S94 S05 2R23 (2/15) 2N2K-RC Inlet W88 S97 S05 2R23 (2/15) 2N3A-MS F80 S91 S97 S05 2R23 (2/15) 2N3B-MS S85 S94 S97 S05 2R23 (2/15) 2N3C-MS F89,92 S00 2R20 (2/09) 2N3D-MS S80 S91 S00 2R20 (2/09) 2N4A (2) FW S80 S82 F86,F89 92,S94 S97 S05 2R23 (2/15) 2N4B (2) FW S80 S82 F86,F89 92,S94 S97 S05 2R23 (2/15) 2N4C (2) FW S80 S82 F86,F89 92,S94 S05 2R23 (2/15) 2N4D (2) FW S80 S82 F86,F89 92,S94 S05 2R23 (2/15) 2N5A-CS S85 S94 S05 2R23 (2/15) 2N5B-CS F89 S00 S05 2R23 (2/15) 2N6A-Spray 80 89,S91 S00 3 2R20 (2/09) 3 2N6B-Spray F89,92 S00 3 2R20 (2/09) 3 2N7-Head Vent 82 F89 S00 3 2R20 (2/09) 3 2N8A-JP Instr F80 F89 S97 S05 2R23 (2/15) 2N8B-JP Instr F86 S97 S05 2R23 (2/15) 2N9 CRD 82 S91 S97 S05 2R23 (2/15) 2N15 Drain (1) (1) (1) (1) 1 st Interval Credit 2 nd Interval Credit 3rd Interval Credit Re-zero exams Notes: 1. The 2N15 RPV drain nozzle is inaccessible because it is located in the center of the bottom head and is surrounded by the CRDs. The SE for RR-3 granted 3 rd interval approval to not perform the required examinations. Similar approval will be required for the 4 th Interval.

2. Multiple examinations due to previous NUREG-0619 requirements.

3. Starting in 2000, 3 rd Interval examinations were enhanced VT-1 per RR-34, Rev.2.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 26 of 43 Rev. 1 Category B-E - Class 1 Partial Penetration RPV Welds Category B-E consists of seven partial penetration welds to the RPV. These are:

2N10 SLC Nozzle (See Sketch 2-BE-3 in Volume 4 of the Ten-Year Exam Plan) 2N11A, B Instrument Nozzles (See Sketch 2-BE-1) 2N12A, B Instrument Nozzles (See Sketch 2-BE-2) 2N16A,B Instrument Nozzles (See Sketch 2-BE-2)

CRD Penetrations - Partial penetration weld is on the inside of the RPV.

1 st and 2 nd Interval An evaluation was not performed for these intervals.

3 rd Interval Table IWB-2500-1 of the 1989 Edition of Section XI requires that 25% of the welds be VT-2, visually examined during the 3 rd Interval; however, examinations may be deferred until the end of the interval. Due to limited access, VT-2 examinations are performed indirectly each refueling outage (as al lowed by IWA-5240) during the leakage and hydrostatic tests (Code Case N-498-1).

4th Interval Not a Code Category in the 2001 Edition th rough the 2003 Addenda; therefore there are no code requirements.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 27 of 43 Rev. 1 Category B-F - Class 1 Dissimilar Metal Piping Welds LESS THAN 4" NPS (B5.20)

Nozzle Requirement Evaluation 2B11\N10 Standby Liquid Control Surface examination of Inconel Nozzle-To-304SS Safe End Inconel 182 weld and butter designated as:

2C41-1SBLC-2-1

This nozzle is located below the core support plate; therefore, any loss of inventory, as a result of a safe-end weld break, would consist of water. Per the 4 th Interval IWB-1220(a) exemption criteria, lines containing water that have an ID of 1.09" are exempt; however, per Sketch 2-BE-3 this line containing weld 2C41-1SBLC-2-1 has an inside diameter of 1.938" and is not exempt from NDE requirements and a Section XI surface examination is required. The safe-end to nozzle was fabricated by welding two solid materials together and boring them out. (ID cold working was introduced; therefore, BWRVIP-27 recommends a complete UT exam of the dissimilar metal weld, the safe-end, and stainless weld from the safe-end side. 2B11\N11A&B Instrument Nozzles No examination requirement for the Inconel Nozzle-To-304SS Safe End Inconel 182 weld and butter because all welds are exempt on size. These instrument nozzles penetrate the RPV at Elevation 509" opposite the steam separator. Therefore, any inventory lost as a result of a safe-end weld break would consist of steam. Per the 4 th Interval IWA-1220(a) exemption criteria, lines containing steam that have an ID of 2.18" or less may be considered exempt. Per Sketch 2-BE-1 the piping on each of these safe-ends has an inside diameter of 1.938"; therefore these welds are exempt. [Per BWRVIP-49, no additional exams are required; therefore no examinations will be performed except for a VT-2 examination during pressure testing]. 2B11\N12A&B Instrument Nozzles

No examination requirement for the Inconel Nozzle-To-304SS Safe End Inconel 182 weld and butter because all welds are exempt on size. These instrument nozzles penetrate the RPV at Elevation 586" opposite the top of the steam separator. Therefore, any inventory lost as a result of a safe-end weld break would consist of steam. Per the 4 th Interval IWA-1220(a) exemption criteria, lines containing steam that have an ID of 2.18" or less may be considered exempt. Per Sketch 2-BE-2 this weld has an inside diameter of 1.938"; therefore these welds are exempt. [Per BWRVIP-49, no additional exams are required; therefore no examinations will be performed except for a VT-2 examination during pressure testing]. 2B11\N15 Bottom Head Drain No examination because the Inconel Nozzle-To-304SS Safe End Inconel 182 weld and butter is inaccessible. Bottom Head Drain. Inaccessible due to location inside support skirt. During the 3 rd Interval, this weld received a VT-2 examination instead of the Code required examination per NRC approved RR-6. A similar Relief request will be needed for the 4 th Interval.

2B11\N16A&B Instrument Nozzles

Surface exam of Inconel Nozzle-To-304SS Safe End Inconel 182 weld and butter designated as:

2B11-1INST-2A-1 2B11-1INST-2B-1 Each of the two instrument nozzles penetrate the RPV in the shroud annulus; therefore, any inventory lost as a result of a safe-end weld break would consist of water. Per the 4 th Interval IWA-1220(a) exemption criteria, lines containing water that have an ID of 1.09" or less may be considered exempt; however per Sketch 2-BE-2, the dissimilar metal joint has an inside diameter of 1.938"; therefore it is not exempt and a Section XI surface examination is required. Per BWRVIP-49, no additional exams are required beyond those required by ASME XI.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 28 of 43 Rev. 1 NPS 4" AND LARGER (B5.10)

Scope: 10 - Recirc. Inlet Safe-End to Nozzle Welds 2 - Recirc. Outlet Nozzle to Safe End Welds 2 - Jet Pump Instrument Nozzle to Safe End Welds 2 - Core Spray Safe-End to Nozzle Welds

3 - RHR stainless steel to carbon steel welds 1 - CRD Return Line Nozzle to Cap 8 - Feedwater Nozzle Safe-End Welds

The Section XI Code requires that 100% of the above dissimilar metal piping welds be examined each interval. Deferral of the examinations until the end of the interval is not permitted.

The weld configuration gene rally consists of Incone l buttered carbon steel to 304 stainless steel with Inconel 182/82 filler metal. Stress improvement to reduce the residual welding stresses has been performed on each of these welds using either Induction Heating Stress Improvement (IHSI) or Mechanical Stress Improvement (MSIP). Generic Letter 88-01 and NUREG-0313 classify these welds as Category C welds. Based on BWRVIP-075, if: (1) an effective stress improvement has been performed, (2)there is a second crack mitigator (e/g. hydrogen water chemistry) and qualified examinations have been performed, then only 10% of Category C welds need to be examined. The implementation of BWRVIP-075 is described in detail in the BWRVIP-075 section of this bases document. Because only 10% of Category C welds is required, the 100% ASME Section XI examination requirement is not being met. Relief was obtained from the NRC via ALT-3 to eliminate the B-F welds from Code required percentages and frequency.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 29 of 43 Rev. 1 Category B-G Class 1 Pressure Retainin g Bolting Greater Than 2" in Diameter The scope consists of RPV and Reactor Recirc. Pump bolting as addressed below.

Configuration The HNP-2 B-G-1 scope consists of:

RPV Bolting 56 RPV Nuts (Item B6.10) - For the 4 th Interval, the 2001 Edition of the Section XI Code through the 2003 addenda requires a vi sual (VT-1) of the nuts. The Code allows deferral of these examinations until the end of the interval; however, this was not used. Instead, during the 3 rd Interval scheduling was performed per Code Case N-598. Continuing the pre-estab lished pattern, 22 nuts (40%) are scheduled for the 1 st Period, 14 nuts (cumulative percentage of 65%) are scheduled for the 2 nd Period, and 20 nuts are scheduled for the 3 rd Period (cumulative percentage of 100%).

56 RPV Studs (Item B6.20) - During the 4 th Interval, examinations will be performed per Code Case N-307-3 and the 2001 Editi on of the Section XI Code through the 2003 addenda. Code Case N-307-3 defines the examination volume. The Code allows deferral of these examinations until the end of the interval; however, this was provision was not used because the 3 rd Interval examinations were distributed into each of the three periods. Continuing the 3 rd Interval establis hed pattern, 22 (40%) are scheduled for the 1 st Period, 14 (cumulative percenta ge of 65%) are scheduled for the 2 nd Period, and 20 are scheduled for the 3 rd Period (cumulative percentage of 100%). 56 RPV Threads in Flange (Item B6.40) - During the 4 th Interval, examinations will be performed per the 2001 Edition of the S ection XI Code through the 2003 addenda. The Code allows deferral of these examinations until the end of the interval; however, this was provision was not used because the 3 rd Interval examinations were distributed into each of the three periods. Continuing the 3 rd Interval established pattern, 22 (40%) are scheduled for the 1 st Period, 14 (cumulative percentage of 65%) are scheduled for the 2 nd Period, and 20 are scheduled for the 3 rd Period (cumulative percentage of 100%).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 30 of 43 Rev. 1 56 RPV Washers (Item B6.50) - For the 4 th Interval, the 2001 Ed ition of the Section XI Code through the 2003 addenda requires a visual (VT-1) of the washers. The Code allows deferral of these examinations until the end of the interval; however, this was provision was not used because the 3 rd Interval examinations were distributed into each of the three periods. Continuing the 3 rd Interval established pattern, 22 (40%) are scheduled for the 1 st Period, 14 (cumulative percentage of 65%) are scheduled for the 2 nd Period, and 20 are scheduled for the 3 rd Period (cumulative percentage of 100%).

Examinations are scheduled as shown in the attached Hatch Unit No.2 Code 4 th Interval Compliance Scheduling Summary.

RC Pumps 32 RC Pump Bolts (Item B6.180 - 16 per pump) - During the 4 th Interval, examinations will be performed per the 2001 Edition of the Section XI Code through the 2003 addenda. The Code requires that the bolts on one of the two pumps be volumetrically examined during the 10-year interval. Deferral unt il the end of the interval is permitted. During 2R16 (2 nd period 3 rd interval), the 16 studs on Pump B were volumetrically examined; therefore, 4 th Interval examinations will be scheduled for the 2 nd Period on Pump B. Note: If disassembled, Footnote 7 allows a surface examination meeting the acceptance standards of IWB-3515 to be used in lieu of the volumetric examination.

Flange Surfaces, when disassembled (Item B6.190) - During the 4 th Interval, examinations will be performed per the 2001 Edition of the Section XI Code through the 2003 addenda. Per Table IWB-2500-1 category B-G-1 footnote 4, visual examinations are only required if a pump is disassembled and subsequently examined per Category B-L-2 requirements. Exam ination is required only once during the interval.

32 RC Pump Nuts (Item B6.200 - 16 per pump) - During the 4 th Interval, examinations will be performed per the 2001 Edition of the Section XI Code through the 2003 addenda. Per Footnote 4, visual examinations are only required if a pump is disassembled and subsequently examined per Category B-L-2 requirements. Examination is required only once during the interval.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 31 of 43 Rev. 1 Interpretation Number: XI-1-98-22 Codebook: Section XI Volume: 0 Date: 03-JUN-98

Subject:

Table IWB-2500-1 (1989 Edition)

Question (1): For those Class 1 pumps not being disassembled during the interval for maintenance, repair, or volumetric examination, is it a requirement of Table IWB-2500-1 to perform B-G-1 bolting examinations on at least one pump in each group of pumps?

Question (2): For those Class 1 valves not being disassembled during the interval for maintenance, repair, or volumetric examination, is it a requirement of Table IWB-2500-1 to perform B-G-2 bolting examinations on at least one valve in each group of valves?

Reply (1): No.

Reply (2): No.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 32 of 43 Rev. 1 Category B-G Class 1 Pressure Retainin g Bolting Less Than or Equal to 2" in Diameter Code Percentages The B-G-2 scope consists of the following bolting. Details are provided below.

1. CRD Flange Bolting

2. Piping Flange Bolting

3. Valve Bolting

1. CRD Flange Bolting (Item B7.80) - The 2001 Edition of the Section XI Code through the 2003 addenda eliminated this Code Item. However, per 10 CFR 50.55a(b)(2)(xxi)(B) the NRC requires that reused bolting be examined whenever the CRD housing is disassembled.

2. Piping Flange Bolting (Item B7.50) - During the 4 th Interval, examinations will be performed per the 2001 Edition of the Section XI Code through the 2003 addenda. Per Footnote 3, the examination is required only when a flange is disassembled. Additionally, examinations may be limited to one bolted

connection among a group of bolted connections that are similar in design, size, function, and service. Examination of a bolted connection is required only once during the interval, regardless of the number of times the bolted connection is disassembled. Groups are listed below.

Component ID Associated Component Group Number 2B21\1CHSV-1FB 2N7 NOZZLE 1 2B21-1MS-8A-ASR-2FB 2B21-F013B 2 2B21-1MS-8A-BSR-2FB 2B21-F013A 2 2B21-1MS-8B-ASR-2FB 2B21-F013K 2 2B21-1MS-8B-BSR-2FB 2B21-F013D 2 2B21-1MS-8B-CSR-2FB 2B21-F013C 2 2B21-1MS-8B-DSR-2FB 2B21-F013E 2 2B21-1MS-8C-ASR-2FB 2B21-F013L 2 2B21-1MS-8C-BSR-2FB 2B21-F013G 2 2B21-1MS-8C-CSR-2FB 2B21-F013F 2 2B21-1MS-8D-ASR-2FB 2B21-F013J 2 2B21-1MS-8D-BSR-2FB 2B21-F013H 2 2B31-1RCM-28AS-9BC-4FB CLEANOUT 3 2B31-1RCM-28BS-8BC-4FB CLEANOUT 3 2E11-1RHR-9A-HS-1FB 2N6A NOZZLE 4 2E11-1RHR-9B-HS-1FB 2N6B NOZZLE 4

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 33 of 43 Rev. 1

3. B-G-2 Valve Bolting (Item B7.70) - (Does not include any flange bolting used to connect the valve to th e piping). During the 4 th Interval, examinations will be performed per the 2001 Edition of the Section XI Code through the 2003 addenda. Per Footnote 2, examination of pressure-retaining valve bolting is required only when Category B-M-2 visual exams are performed on the inside surface of the valve (see Interpretation XI-1-98-22). B-M-2 examinations are only required at HNP when a valve is disassembled for maintenance or repair, and only one valve in a like group of valves requires examination, regardless of how many valves are dissembled during th e interval. Theref ore, scheduling of valve bolting is not require

d. Valve bolting and the a ssociated valve group are listed below:

Valve Bolting Valve Group Number 2B21-F010A&B and F077A&B VB 1 2B21-F011A&B VB 2 2B21-F013A, B, C, D, E, F, G, H, K, L, M VB 3 2B21-F022A thru D and F028A thru D VB 4 2B31-F023A&B and F031A&B VB 5 2E11-F008 and F009 VB 6 2E11-F015A&B VB 7 2E11-F067 VB 8 2E11-F050A&B VB 9 2E11-F060A&B VB 10 2E21-F004A&B and F005A&B VB 11 2E21-F006A&B VB 12 2E21-F007A&B VB 13 2E41-F006 VB 14 2E41-F002 and F003 VB 15 2G31-F001 and F004 VB 16 2G31-F027 VB 17

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 34 of 43 Rev. 1 Category B-J - Class 1 Piping Welds

Background

10 CFR 50.55a(b)(2)(ii) states, "Pressure-retaining welds in ASME Code Class 1 piping (applies to Table IWB - 2500 and IWB - 2500 - 1 and Category B - J). If the facility's application for a construction permit was doc keted prior to July 1, 1978, the extent of examination for Code Class 1 pipe welds may be determined by the requirements of Table IWB - 2500 and Table IWB - 2600 Category B - J of Section XI of the ASME Code in the 1974 Edition and addenda through the Summer 1975 Addenda or other requirements the Commission may adopt."

The construction permit for HNP-2 was docke ted on 12/27/72 which allowed the use of 10 CFR 50.55a(b)(2)(ii); th erefore, during the 2 nd and 3 rd Interval updates, HNP-2 elected to use the provisions 10 CFR 50.55a(b)(2)(ii). HNP-2 used the 1974 Edition and addenda through the Summer 1975 Addenda during the 1 st Interval; therefore, the use of the above provision essentially allowed the same non-exem pt Category B-J welds to be selected for the 2 nd and 3 rd Intervals with the following caveats.

The 1974 Edition and addenda through the Summer 1975 actually requires a different 25% sampling of welds be performed each 10-year interval. Subsequent Code editions had a philosophical change - determine a sample to examined and then repeat the examination each 10-year interval. This later philosophy was utilized.

Terminal ends and high stress welds were chosen as practical to upgrade the overall selection criteria. All other requirements for B-J piping are from the 1989 Edition of Section XI.

Relief was obtained (RR-39) during the 3 rd Interval to not meet two Code requirements for stainless steel and dissimilar metal welds because they are examined per the BWRVIP-75 augmented program. These requirements are:

1. IWB-2412 requires that except for the examinations that may be deferred until the end of the inspection interval, examinations shall be completed in accordance with Table IWB-2412-1. Table IWB-2412-1 defines a minimum and maximum number of examinations to be performed each inspection period.

2. IWB-2500 requires components to be examin ed as specified in Table IWB-2500-1.

The Extent and Frequency of Examination requires that all Category B-F welds be examined and that a minimum of 25% of Category B-J welds be examined over the ten-year ISI interval.

In lieu of the above Code requirements, the schedules and frequencies specified in the BWRVIP-75 will be used.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 35 of 43 Rev. 1 4 th Interval ISI-ALT-3 was submitted to the NRC (and approved) to continue the process initiated by RR-39; therefore, those welds covered by the provisions of BWRVIP-075 are not included as Category B-J.

(See Category XB-J).

As allowed by 10CFR50.55a(b)(2)(ii), Category B-J welds to be examined in Interval 4 will be those selected during Interval 3. However, the scope will again be slightly adjusted to enhance the examination population based on guidance from Code Case N-609. Code Case N-609 provides an alternative to Code stress-based criteria for the selection of welds and was approved for us e by the NRC in Revision 14 to Regulatory Guide 1.147. This code case has three featur es that were cons idered as possible enhancements. These features and any changes to 3 rd Interval scope are addressed below:

1. Select all terminal ends. (Note: Terminal ends are the extremities of piping runs that connect to vessels, pumps, valves, piping systems, structures, or pipe anchors, each which acts as a rigid restraint or provides at least 2 degrees of restraint to piping thermal expansion. (The problem with examining all of the terminal ends is that, in many cases, there are severe coverage restrictions). The HNP terminal ends are evaluated below and any changes to the scope were identified.

There are four feedwater nozzles and four main steam nozzles where the weld to the nozzle is a terminal end. A ll eight are scheduled for the 4 th Interval.

There are containment penetrations with a weld to the flued head located outside the penetration. This is an anchor po int for stress analysis, but is not the extremity of the piping run; therefore, it is not considered a terminal end. Six were examined in the 3 rd Interval. No change will be made for the 4 th Interval.

There are 13 cases where a smaller line terminates at a branch connection on a larger line. For the connection of a pipi ng run to a piping run, there is a rule-of-thumb for coupling or de-coupling piping runs when performing a stress analysis.

This is, when the ratio of the piping diamet ers is 10 to 1 or greater, the connection is considered to be a terminal end. None of the 13 cases had a 10/1 or greater ratio; therefore, there are no terminal ends in this population. A total of 3 of the 13 were examined during the 3 rd Interval. For the 4 th Interval, no additional welds were selected.

2. Select dissimilar metal welds not cove red under Category B-F. There are no Category B-J dissimilar metal welds. Dissimilar metal welds greater than or equal to 4" in diameter are designated as Category XB-F and are examined per VIP-075 (see VIP-075 section). Those under 4" ar e designated as Category B-F.

3. Select additional piping welds, such that the total number of circumferential butt welds (or branch connection or socket welds) selected for examination equals 25% of the total number of nonexempt circumferential butt welds (or branch connection or HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 36 of 43 Rev. 1 socket welds) in the reactor coolant piping system. The examinations were prorated among the Class 1 systems on the number of nonexempt welds in each system. Additionally, within each system, examina tions were distributed between line sizes prorated, on the number of nonexempt welds in each line size. Because this was an enhancement, actual proration was not met; however, as shown in the below table, welds selected are spread throughout the systems and different line sizes.

Size System No. of Welds Welds Selected For Examination Percentage 12" FW 45 11 24% 18" FW 20 4 20% 4" MS 1 0 0% 24" MS 89 25 28% 8" MS 22 6 27% 20" RHR 10 3 30% 24" RHR 24 6 25% 9" RHR 2 1 50% 10" CS 41 10 24% 10" HPCI 22 7 32% 4" RCIC 19 6 32% TOTAL 295 79 27%

As discussed above in the Exemptions Section, the IWB-1220(a) exemption criteria changed which required adding numerous small diameter welds to the 4 th Interval examination population. A summary of theses welds is shown below.

SMALL DIAMETER CATEGORY B-J WELDS ADDED FOR THE 4 TH INTERVAL (Shown as Category NB-J in Schedule Works) Size System No. of Welds Welds Examined Percentage 1.5" SBLC 84 23 14% 2" SBLC 75 17 11% TOTAL 159 40 25%

These examinations are not deferrable until the end of the interval per the 2003 Addenda; therefore, the scheduling requirements of IWB-2412-1 are required.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 37 of 43 Rev. 1 Category B-K - Class 1 Welded Attachments

Background

In lieu of the 3 rd Interval 1989 Code requirements for welded attachments, HNP examined Class 1 welded attachments per the requirements of Code Case N-509, which was originally adopted for use at HNP th rough relief request RR-4.

Relief Request RR-4 was superseded via the endorsement of Code Case N-509 in Revi sion 12 to Regulatory Guide 1.147. Revision 13 subsequently annu lled the Code Case; however, it was used until the end of the 3 rd Interval. Revision 12 had a conditi on for use, in that, at least 10% of each Item No. was required to be examined (for those items not already requiring 100%). Beyond those requirements established below, examination of an integrally welded attachment is required if the associated component support member has deformation identified during operation, refueling, maintenance, examination, in service inspection, or testing. An example of component support deformation is broken part s, bent parts, or pulled out parts.

Additionally, Relief Request RR-41 which adopted Code Case N-700 was submitted (and approved by the NRC) during the 3 rd Interval to effectively eliminate the examination of the stabilizer brack ets (for Unit 1).

4 th Interval Examinations are required per the 2001 Ed ition of Section XI with Addenda through 2003, as modified by 10 CFR 50.55a(b)(2)(xxi)(C).

Deferral of the examinations until the end of the Interval is not permitted.

Item B10.10 - Pressure Vessels: The only Class 1 pressure vessel is the reactor pressure vessel (RPV). With a single vessel, the Code requires the examination of all welded attachments. The HNP-2 RPV is supported by a reactor skirt (Weld C-6) and has six stabilizer brackets (SB1 - SB6) welded to the shell to prevent the RPV from tilting during a seismic event. The inside surface of the support skirt weld (C-6) is totally inaccessible for examination. Note: The RPV head has lifting lugs which are not considered to be in the Examination Category B-K scope. The basis for this determination is that Examina tion Category B-K, Table 2500-1, Footnote 1 indicates that examination is limited to those attachments providing component support per NF-1110. NF-1110 indicates that this applies only to metal elements which transmit loads between component s and the building structure.

Per 10 CFR 50.55a(b)(2)(xxi)(C), the provis ions of Table IWB-2500-1, 1995 Addenda must be applied to Item B10.10. The 1995 addenda allows a volumetric examination of the skirt weld if the skirt weld configuration is that shown in Figure IWB-2500-14. For HNP-2, the configuration does not match Figure 14; therefore, HNP will use Code Case HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 38 of 43 Rev. 1 N-323-1 for the examination of the support sk irt weld. Code Case N-323-1 allows a surface examination from the accessible surface (outside) as an alternative if the inside surface is inaccessible.

Per footnote 4 of the Code, when there are multiple vessels, only one welded attachment weld on one of the vessels requires examina tion. However, when there is a single vessel (such as the RPV), footnote 4 does not apply and all of the welded attachment welds require examination. Code Case N-700 was developed to align the examination requirements for single vessels with those for multiple vessels. SNC proposes using Code Case N-700 to select RPV welded attachments for examination in lieu of using the Code Case N-509 footnote 4 requirements.

Code Case N-700 states that, "For single vessels, only one welded attachment shall be selected for examination. The attachment selected for examination on one of the multiple vessels or the single vessel, as applicable, shall be an at tachment under continuous load during normal system operation, or an attachment subject to a potential intermittent load (seismic, water hammer, etc.) during normal system operation if an attachment under continuous load does not exist." The exam ination of the HNP-2 RPV skirt weld will satisfy Code Case N-700 examination requirements because this weld is under a continuous load during normal system operati on, while the stabili zer bracket welds are potentially loaded only during a major seismic event.

MONITOR THE INCLUSION OF N-700 INTO REGULATORY GUIDE 1.147 OR DEVELOP AN ALTE RNATIVE (SEE 3 rd INTERVAL RR-41)

Item B10.20 - Piping: Per the Code, 10% of the piping welded attachments must be examined. There are 28 sets of welded attachments in the Class 1 scope. For the purpose of this discussion, a set is a group of welded attachments associated with a specific location. For instance, a hanger clamp may have four welded lugs but it is considered one set. When a set of welded attachments is selected for examination all of the welded attachments in that set should be examined.

10% of 28 sets would require the examination of 3 sets of welded attachments.

Note: Containment penetrations are show n on FSAR Figure 3.8-2, sheets 1, 2 , and 3.

Sheets 1 and 2 are for flued head type penetrations; therefore, there are no attachments welded to the piping pressure boundary. Sheet 2, which applies to the Main Steam penetrations shows a welded attachment to the pressure boundary. These welded attachments are designated as 18PS on Figures A-6 and A-9 and are designated as 16PS on Figures A-7 and A-8. These four welded attachments are include d in the total of 28.

Item B10.30 - Pumps: Per the Code, 10% of the welded attachments must be examined. There are 3 Class 1 attachments on each of the two pumps requiring a total of one examination to be performed.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 39 of 43 Rev. 1 Category B-L Pressure Retaining Welds in Pump Casings NA to Hatch.

Category B-L Pump Casings There are two Class 1 pumps at Hatch - the Recirculation System Pumps. The following 2001 Edition through the 2003 Addenda Code requirements apply.

1. If one of the two pumps is disassembled for maintenance or repair, a VT-3 examination of the accessible internal pressure boundary should be performed to the extent practical. Examinations are limited to one pump in the 10-year interval; therefore, if one of the two pumps is examined there are no other examination requirements for the 10-year interval.

2. There is not a requirement to disassemble a pump in order to perform the VT-3 examination.

3. There is not a requirement to completely disassemble a pump that has been partially disassembled for maintenance or repair. For a partially disassembled pump, examine the accessible portion of the internal pressure boundary.

4. If a pump has been partially disassembled and VT-3 examined and subsequently one of the pumps is disassembled such that a more extensive examination is allowed, re-perform a VT-3 examination on the disassembled pump.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 40 of 43 Rev. 1 Category B-M Pressure Retaining Welds in Valves NA to Hatch.

Category B-M Valve Body Greater Than 4" NPS Examinations (VT-3) are limited to one valve in each group of valves that are of the same size, constructional detail (e.g. globe), manufacturing method, and that perform similar functions in the system. The groupings are shown in Table 1-10.

1. If one of the valves in Table 1-5 is disassembled for maintenance or repair, a VT-3 examination of the accessible internal pressure boundary should be performed to the extent practical. Examinations are limite d to one valve in the group in the 10-year interval; therefore, if one of the valves in a group is examined there are no other examination requirements for that group duri ng the 10-year interval. Third Interval examinations are shown in Table 1-5.

2. There is not a requirement to disassemble a valve in order to perform the VT-3 examination.

3. There is not a requirement to completely di sassemble a valve that has been partially disassembled for maintenance or repair. For a partially disassembled valve, examine the accessible portion of the in ternal pressure boundary (see Interpretation XI-1-01-12 below).

4. If a valve has been partially disassembled and VT-3 examined and later one of the valves in the same group is disassembled such that the coverage is significantly greater, perform a VT-3 examination on the recently disassembled valve.

Interpretation Number: XI-1-01-12 Codebook: Section XI Volume: 48 Date: 13-DEC-00

Subject:

Table IWB-2500-1 (1986 Edition with 1986 Addenda through 1992 Edition with 1993 Addenda) Is it a requirement of Table IWB-2500-1 to disassemble all internal components of a valve at least once in an inspection interval, in order to perform the VT-3 required by Category B-M-2, Item Number B12.50, even though the maintenance activity, repair, or volumetric examination may not require disassembly of some of the internal components?

No. Examination of the internal pressure boundary is required to the extent practicable.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 41 of 43 Rev. 1 Category B-N RPV Interior See Vessel Internals Notebooks Category B-N RPV Core Support Structure and Attachments See Vessel Internals Notebooks

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 42 of 43 Rev. 1 Category B-O - Pressure Retaining Welds in Control Rod Drive (CRD) Housings The bottom head of the RPV has a penetration for each CRD location. Each penetration has an Inconel SB-167 stub tube welded to the inside surface of the RPV bottom head with an Inconel 182 weld. Each CRD housing was raised into position inside the stub

tube and fastened with a J-Groove weld to the stub tube. The J-Groove weld had an Inconel 82 root with the rema inder Inconel 182. Outside of the RPV, there is a housing to flange weld and an intermediate housing to housing weld between the flange weld and the bottom of the vessel. (S ee Figure 2-BN-14-1 and A-29).

The 2001 Edition with 2003 Addenda Code requirement is to perform a volumetric or surface examination of 10% of the welds located in the peripheral CRD housings. However, the examination is not required if the makeup flow specified in IWB-1220(a) is greater than the postulated loss of inventory caused by the failure of the weld. Per the Exemption Section of this document the makeup flow is 420 gpm and per Section 4.2.3.2.3.1 of the HNP UFSAR (shown below), the leak rate from the housing to flange weld failing in tension would be limited to ~ 840 gpm and the leak rate from a housing rupture would be ~ 1030 gpm. Therefore, the examination is not exempt per Section XI because the makeup flow is insufficient. There are 36 peripheral CRD housings per Figure 2-BN-15-1; therefore two welds on four housings require examination.

Each of the two welds outside of the RPV are stainless to stainless welds and may have some susceptibility to IGSCC dependent upon the degree of hydrogen water chemistry protection.

Weld Joining Flange to H ousing Fails in Tension The failure considered is a crack in or near the weld that joins the flange to the housing. This crack will extend through the wall and completely around the housing. The flange material is forged, Type 304 stainless steel, wi th a minimum tensile strength of 75,000 psi.

The housing material is seamless, Type 304 st ainless-steel pipe, with a minimum tensile strength of 75,000 psi. The conventional full-penetration weld of Ty pe 308 stainless steel has a minimum tensile strength approximately the same as that for the parent metal. The design pressure and temperature are 1250 psig and 575 0 F, respectively. RPV pressure acting on the cross-sectional area of the CRD; the weight of the control rod, CRD, and flange; and the dynamic reaction force during CRD operation result in a maximum tensile stress at the weld of ~ 6000 psi. If the basic flange-to-housing joint failure occurs, the flange and the attached CRD are blown dow nward against the support structure. The support structure loading is slightly less than that for CRD housing failure because RPV pressure acts only on the CRD cross-sectional area. Lack of differential pressure across the collet piston causes the collet to remain latched and limit control rod motion to ~ 3 in. Downward CRD movement is small; therefor e, most of the CRD remains inside the housing. The pressure-under and pressure-over lines are flexible enough to withstand the small displacement and remain attached to the flange. RPV water follows the same leakage path described for the flange-bolt failure, except that exit to the atmosphere will be through the gap between the lower end of th e housing and the top of the flange. Water flashes to steam in the annulus surrounding the CRD. The leakage rate is ~ 840 gal/min.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS H2 Basis Doc - Class 1 Page 43 of 43 Rev. 1 Class 1 Augmented Examinations The NRC's safety evaluation dated 6/16/97 of the 3 rd Interval ISI Program indicated, that in addition to the 1989 Code required examinations, certain Class 1 augmented examinations would be performed per GPC commitment. The commitments along with the current implementation methodology are listed below.

1. Augmented examinations on the Unit 2 main steam, feedwater, HPCI (steam),

RCIC (steam) and RWCU high energy piping outside containment (where pipe breaks were not postulated) in compliance with Branch Technical Position MEB 3-1. Per Section 3.6.2.2.3 of the HNP-2 UFSA R, pipe breaks we re not postulated in portions of high-energy piping extending from the containment penetration to the first inside and/or outside isolation valve for specified conditions. Therefore, for the above mentioned systems, volumetric exams are required on the welds

between the inboard and outboard isolation valves to the extent practical. These examinations will be performed during the 4 th Interval, to the extent practical.

HIGH ENERGY "NO-BREAK" ZONE WELDS Weld Fig Weld Fig 2B21-1FW-18A-1 A-12 2B21-1MS-24D-18 A-9 2B21-1FW-18A-1A A-12 2B21-1MS-24D-19 A-9 2B21-1FW-18A-2 A-12 2B21-1MS-24D-20 A-9 2B21-1FW-18B-1 A-13 2E41-1HPCI-10-D-19 A-26 2B21-1FW-18B-1A A-13 2E41-1HPCI-10-D-20 A-26 2B21-1FW-18B-2A A-13 2E41-1HPCI-10-D-21 A-26 2B21-1MS-24A-18 A-6 2E41-1HPCI-10-D-22 A-26 2B21-1MS-24A-19 A-6 2E51-1RCIC-4-D-16A A-27 2B21-1MS-24A-20 A-6 2E51-1RCIC-4-D-17 A-27 2B21-1MS-24B-16 A-7 2E51-1RCIC-4-D-18 A-27 2B21-1MS-24B-17 A-7 2E51-1RCIC-4-D-19A A-27 2B21-1MS-24B-18 A-7 2G31-1RWCU-6-D-17 A-28 2B21-1MS-24C-16 A-8 2G31-1RWCUM-6-D-15 A-28 2B21-1MS-24C-17 A-8 2G31-1RWCUM-6-D-16 A-28 2B21-1MS-24C-18 A-8 2. Augmented examination of welds suscepti ble to IGSCC as specified in NUREG-0313 as modified by Generic Letter 88-01. These examinations are currently performed per BWRVIP-075. See the BW RVIP-75 Section of this document.

3. Augmented exams of the feedwater nozzles as specified by NUREG-0619 as modified by Generic Letter 81-11. These exams were originally performed as required. They are currently performe d per "Alternate BWR Feedwater Nozzle Inspection Requirements," GE-NE-523-A71-0594-A, Revision 1, May 2000.

Southern Nuclear Operating Company 3 Page 1 - 1 1/9/2006 Table IWB-2500-1, Footnote 2 allows 25% to 50% to be examined during Period 1 and the balance by the end of the Interval.

I I I Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 Rev. 1.0 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS 8-D 83.100 29 96.55% 28 28 28 8-D 83.90 29 96.55% 28 28 28 Total: 58 56 56 56 ACTUAL ROUND COUNT PERIOD UP 9 32.14% 33% 9 32.14% 33% 18 32.10%

33% ACTUAL ROUND COUNT PERIOD UP 0 32.14% 33% 0 32.14% 33% 0 32.10% 33% ACTUAL ROUND COUNT PERIOD UP 19 100.00%

100% 19 100.00%

100% 38 100% 100%

Southern Nuclear Operating Company Page I - 11/9/2006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERCENT ACTUAL ROUND TOTAL 1 ACTUAL ROUND 1 ACTUAL ROUND B-G-1 B6.180 B-G-1 B6.190 B-G-1 B6.20 B-G-1 86.200 B-G-1 86.40 B-G-1 B6.50 Total: CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-G-1 B6.10 57 100% 57 57 57 COUNT PERIOD UP 14 64.91% 65% 16 100.00% 100% 0 0% 0% 14 65.52% 66% 0 0% 0% 14 64.91% 65% 14 64.91% 65% 72 67.30% 68% COUNT PERIOD UP 23 40.35%

41% PERIOD 3 ACTUAL ROUNI COUNT PERIOD UP B6.190 and B6.200 exams are not required unless a pump is disassembled.

Then, only one pump is required to be examined.

I I I I Rev. 1.0 Southern Nuclear Operating Company Page I - 111912006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL 1 ACTUAL ROUND 1 ACTUAL ROUND 1 ACTUAL ROUND Examinations are not required unless a component is disassembled.

Then, only one in a group requires examination.

CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-G-2 B7.50 16 0% 0 0 0 B-G-2 87 70 52 0% 0 0 0 Total. 68 0 0 0 Rev. 1.0 COUNT PERIOD UP 0 0% 0% 0 0% 0% 0 0% 0% COUNT PERIOD UP 0 0% 0% 0 0% 0% 0 0% 0% COUNT PERIOD UP 0 0% 0% 0 0% 0% 0 0% 0%

Southern Nuclear Operating Company Page 1 - 1 119l2006 The required percentage is based on Table IWB-2412-1 and applies only to the total, not each item number. Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 Rev. 1.0 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-J 89.11 282 25% 70.5 7 1 97 B-J 89.31 13 25% 3.25 4 4 Total: 295 73 75 101 ACTUAL ROUND COUNT PERIOD UP 23 32.62%

33% 2 61.54% 50% 25 34.20% 34% ACTUAL ROUND COUNT PERIOD UP 24 66.67% 67% 0 61.54% 50% 24 67.10% 66% ACTUAL ROUND COUNT PERIOD UP 50 137.59% 137% 2 123.08% 100% 52 138.00% 134%

Southern Nuclear Operating Company Page I - 111912006 PERIOD 3 ACTUAL ROUND 133.33% 100% 100% 100% Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 The required percentage is based on Table IWB-2412-1 and applies only to the total, not each item number, PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS NB-J 89.21 3 25% 0.75 1 1 NB-J 89.40 156 25% 39 39 39 Total: 159 40 40 40 Rev. 1.0 ACTUAL ROUND COUNT PERIOD UP 1 133.33%

100% 8 20.51% 21% 9 22.50% 23% ACTUAL ROUND COUNT PERIOD UP 0 133.33%

100% 15 58.97% 59% 15 60% 60%

Southern Nuclear Operating Company Page 1 - 1 111 012006 When Code Case N-700 is approved in RG 1.47lR15, the B1O.10 population will drop to 1 (only the support skirt will be examined).

Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 At that time, 2 exams will be performed during each period. Rev. 1.0 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-K 810.10 N-323-1 1 100% 1 1 1 B-K 810.10 6 100% 6 6 6 B-K 810.20 28 10% 2.8 3 4 8-K 810.30 6 10% 0.6 1 1 Total: 41 11 11 12 ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 0 0% 0% 1 35.71% 34% 1 166.67% 100% 2 18.10% 19% ACTUAL ROUND COUNT PERIOD UP 1 100.00% 100% 1 16.67% 17% 1 71.43% 67% 0 166.67% 100% 3 45.40% 46% ACTUAL ROUND COUNT PERIOD UP 0 100.00% 100% 5 100.00% 100% 2 142.86% 134% 0 166.67% 100% 7 109.00% 109%

Southern Nuclear Operating Company Page 1 - 1 111 012006 Examination of the pump casings are not required unless a pump is disassembled.

Then, only one pump needs examination. Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 Rev. 1.0 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-L-2 B12.20 2 0% 0 0 0 Total: 2 0 0 0 ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 0 0% 0% ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 0 0% 0% ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 0 0% 0%

Southern Nuclear Operating Company 3 Page 1 - 1 111 012006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 ACTUAL ROUND 1 C0;NT PEED ;: 1 Examinations are not required unless a valve is dissassembled.

Then, only one in a group requires examination.

ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 0 0% 0% PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS 8-M-2 812.50 5 1 0% 0 0 0 Total: 5 1 0 0 0 Rev. 1.0 ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 0 0% 0%

Southern Nuclear Operating Company Page 1 - 1 111 012006 Rev. 1.0 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS 6-0 614.10 72 10% 7.2 8 8 Total: 72 7 8 8 ACTUAL ROUND COUNT PERIOD UP 2 27.78% 25% 2 28.50% 25% ACTUAL ROUND COUNT PERIOD UP 4 83.33% 75%

4 85.70% 75% ACTUAL ROUND COUNT PERIOD UP 2 111.11% 100% 2 114.00% 100%

3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 - 4 711 212006 I Period 1 Period 2 Period 3 Category, lso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B -A H2 281 1QC-2 RPV lSllUT1 A-1 IS1 Blll(2) 2811QC-2RPV SHELL AUG 1 811 om PRE B A H2 281 1QC-3 RPV ISIIUTI A-1 IS1 81 11 (2) 281 1 QC-3 RPV MIDDLE SHELL AUG 1 811 om PRE B A H2 281 1QC-4 RPV ISIIUTI A-1 IS1 81.11(2) 281 1QC-4 RPV SHELL WELD AuG 1 811 om PRE B-A H2 281 1QC-5 RPV ISIIUTI A- 1 IS1 Blll(2) 2811QC-5RPV TORUS AUG 1 811 om PRE B -A H2 281 1 QC-1 -A ISIIUTI A-1 IS1 81.12(2) 281 1QC-1-A LONGITUDINALWELDONUPPERSHELL AUG 1 Bll ow PRE B -A H2 281 1QC-1-8 ISIIUTI A- I IS1 Bl 12(2) 2811QC-1-8 LONGITUDINALWELDONUPPERSHELL AUG 1 811 om pRE B -A H2 281 1 QC-1 -C lSllUT1 A- 1 IS1 B1.12(2) 281 1QC-1-C LONGITUDINALWELDONUPPERSHELL AUG 1 Bll om PRE B -A H2 281 1 PC-2-A ISIIUTI A- 1 IS1 81.12(2) 281 1QC-2-A SHELL AUG 1 811 om PRE B A H2 281 1 QC-2-8 lSllUT1 A- 1 IS1 81 12(2) 281 1QC-2-8 SHELL AUG 1 811 OWN PRE B A H2 281 1QC-2-C ISIIUTI A- 1 IS1 81 12(2) 281 1QC-2-C SHELL AUG 1 811 ow PRE F 2 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - ---------s-. - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - - - - - - - - - - - - - mo 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - ------- - - - - - - - - - - - - Nt9 2 2 5 5 - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - -s-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s-- - - - - - - - - - - - - - - - - - - - - - - - - -- s-- - - - - - - - - - - - -

3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 2 - 4 711 212006 ( Period 1 Period 2 Period 3 N rn 2 2 5 5 - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - S-- - - - - - - - - - - - - -S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. IternNO, Cornp. Desc. Class Summary 1 CornplD 1 System Scope 1 Method 1 Procedure Code Case B -A H2 281 1PC-3-A ISIIUTI A-1 IS1 B1.12(2) 281 1 PC-3-A SHELL AUG 1 B11 ow PRE B A H2 281 1 PC-3-8 ISIIUTI A-1 IS1 B1.12(2) 2B11PC-3-8 SHELL AUG 1 B11 OWN PRE B -A H2 281 1 PC-3-C ISIIUTI A-1 IS1 B1.12(2) 281 1 PC-3-C SHELL AUG 1 B11 OWN PRE 6-A H2 281 1 '2C-4-A ISIIUTI A-1 IS1 B1.12(2) 2B11PC-4-A SHELL AUG 1 Bll OWN PRE B -A H2 281 1 PC-4-8 ISllUTl A- 1 IS1 Bl .l2(2) 281 1PC-4-8 SHELL AUG 1 B11 ow PRE B -A H2 281 1 '2C-4-C ISllUTl A-1 IS1 B1.12(2) 2B11PC-4-C SHELL AUG 1 Bll OWN PRE B -A H2 281 1PC-7 RPV ISIIUTI A-1 A IS1 B1.21(2) 281 1 \2C-7 RPV HEAD DOME AUG 1 B11 om PRE B -A H2 281 1 PHC-1 ISIIUTI A-3 IS1 B1.21(2) 281 1\2HC-1 DOLLAR PLATE WELD CLOSURE HEAD AUG 1 B11 OWN PRE B -A H2 281 1PBHD-A ISIIUTI A-1 A IS1 B1.22(2) 2BllPBHD-A WELD AUG 1 B11 om PRE B -A H2 281 1 PBHD-B ISIIUTI A-1 A IS1 B1.22(2) 281 1PBHD-B WELD AUG 1 Bll OWN PRE m o & 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - ---------S-- - - - - - - - . - - - -

Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc.

Class Summary 1 ComplD I System Scope 1 Method 1 Procedure Code Case B A H2 281 1UBHD-C ISIIUTI A-1 A IS1 B1.22(2) 2BllUBHD-C WELD AUG 1 B11 OWN PRE B A H2 281 1 UBHD-D ISIIUTI A-1 A IS1 B1.22(2) 2BllUBHD-D WELD AUG 1 B11 OWN PRE B A H2 281 1UBHT-A ISIIUTI A-1 A IS1 B1 22(2) 2BllUBHT-A WELD AUG 1 B11 OWN PRE 6 A H2 281 1UBHT-B ISIIUTI A-1 A IS1 B1.22(2) 2BllQBHT-B WELD AUG 1 B11 OWN PRE B A H2 281 1 UBHT-C ISllUTl A-1 A IS1 B1.22(2) 281 1 UBHT-C WELD AUG 1 B11 OWN PRE B -A H2 281 1 UBHT-D ISIIRTI A-1 A IS1 B1.22(2) 281 1UBHT-D WELD AUG 1 Bll OWN PRE B A H2 281 1QBHT-E ISIIUTI A-1 A IS1 B1.22(2) 281 1 UBHT-E WELD AUG 1 B11 OWN PRE B -A H2 281 1 UBHT-F ISIIRTI A-1 A IS1 B1.22(2) 281 1 UBHT-F WELD AUG 1 B11 OWN PRE B A H2 281 1 UBHT-G ISIIUTI A-1 A IS1 B1.22(2) 2BllUBHT-G WELD AUG 1 B11 OWN PRE B -A H2 281 1 UHC-1 -A ISIIUTINMP-ES-024-503 A-3 IS1 B1.22(2) 281 1UHC-1-A MERlDlONAL WELD CLOSURE HEAD AUG 1 Bll OWN PRE Period 1 0) 0 E 2 5 5 Page 3 - 4 Period 2 Period 3 3 Revision:

1 3 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Cornp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case 8 -A H2 281 1PHC-1-B ISIIUTINMP-ES-024-503 A-3 IS1 B1.22(2) 2B11 PHC-1 -B MERlDlONAL WELD CLOSURE HEAD AUG 1 B11 OWN PRE B A H2 281 1 PHC-1 -C ISIIUTINMP-ES-024-503 A-3 IS1 B1.22(2) 281 1 PHC-1 -C MERlDlONAL WELD CLOSURE HEAD AUG 1 B11 OWN PRE B A H2 281 1 PHC-1 -D ISIIUTINMP-ES-024-503 A-3 IS1 B1.22(2) 281 1PHC-1-D MERlDlONAL WELD CLOSURE HEAD AUG 1 B11 OWN PRE BA H2 281 1 PHC-1 -E ISllUTINMP-ES-024-503 A-3 IS1 B1.22(2) 2811 PHC-1-E MERlDlONAL WELD CLOSURE HEAD AUG 1 B11 OWN PRE 8 -A H2 281 1 PHC-1 -F ISIIUTINMP-ES-024-503 A-3 IS1 B1.22(2) 281 1 PHC-1 -F MERlDlONAL WELD CLOSURE HEAD AUG 1 B11 OWN PRE B A H2 281 1 PHC-1 -G ISIIUTINMP-ES-024-503 A-3 IS1 B1.22(2) 281 1 PHC-1-G MERlDlONAL WELD CLOSURE HEAD AUG 1 B11 OWN PRE 8 -A H2 281 1 PHC-1 -H ISIIUTINMP-ES-024-503 A-3 IS1 B1.22(2) 281 1 PHC-1 -H MERlDlONAL WELD CLOSURE HEAD AUG 1 Bl 1 OWN PRE B A H2 281 1PC-1 ISIIUTI A-1 IS1 B1.30(2) 281 1 PC-1 VESSEL-TO-FLANGE AUG 1 B11 OWN PRE B A H2 281 1 PHC-2 ISIIMTINMP-ES-024-401 A-3 IS1 B1.40(2) 2B11 PHC-2 ISIIUTINMP-ES-024-503 CLOSURE HEAD-TO-FLG AUG 1 B11 OWN PRE Period 1 m 0 2 2 5 5 Page 4 - 4 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval class I IS1 Plan Southern Nuclear Operating Company Period 1 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope 1 Method I Procedure Code Case B -D H2 281 1PN15 (IR) 83.100 2B11QN15 (IR) BOTfOM HEAD DRAIN-RR REQUIRED AUG 1 61 1 OWN PRE B -D H2 2BllQN15 (SH-N) A-I A IS1 83.90 2811 QN15 (SH-N) BOTfOM HEAD DRAIN-RR REQUIRED AUG 1 B11 OWN PRE B -D H2 2011PNlA (IR) ISIIUTI A- 1 IS1 63.100 2B11PNlA (IR) A LOOP RC OUTLET NOZZLE IR AUG 1 B11 OWN PRE B-D H2 281 1QNlA (SH-N) ISIIUTI A-1 IS1 83.90 281 1 PN1 A (SH-N) A LOOP RC OUTLET SHELL TO NOZ AUG 1 B11 OWN PRE B-D H2 281 1 PN1 B (IR) ISllUTl A-1 IS1 83.1 00 281 1 QN1 B (IR) B LOOP RC OUTLET NOZZLE IR AUG 1 Bl I OWN PRE B-D H2 281 1 PN1 B (SH-N) ISllUTl A-I IS1 63.90 2B11QNI B (SH-N) 6 LOOP RC OUTLET SHELL TO NOZ AUG 1 61 1 OWN PRE B -D H2 281 1PN2A (IR) ISllUTl A-1 IS1 83.100 2B11QN2A (IR) B LOOP RC INLET NOZZLE IR AUG 1 Bl I OWN PRE B-D H2 281 1 PN2A (N-SH) lSllUT1 A-I IS1 83.90 261 1 PN2A (N-SH) B LOOP RC INLET NOZZ TO SHELL AUG 1 B11 OWN PRE B-D H2 281 1\2N2B (IR) ISIIUTI A-I IS1 83.100 281 1 QN2B (IR) B LOOP RC INLET NOZZLE IR AUG 1 61 1 OWN PRE B-D H2 281 1PN2B (N-SH) ISllUTl A-I IS1 83.90 261 1 QN26 (N-SH) B LOOP RC INLET NOZZ TO SHELL AUG 1 61 I OWN PRE Page 1 - 6 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval class 1 IS1 Plan Southern Nuclear Operating Company Page 2 - 6 711 212006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Class Summary / ComplD / System Scope / Method / Procedure Code Case B-D H2 281 1PN2C (IR) ISI/UT/ A-1 IS1 83.100 281 1 PN2C (IR) B LOOP RC INLET NOZZLE IR AUG 1 Bll om PRE B-D HZ 281 1PN2C (N-SH) ISIIUTI A-1 IS1 83.90 281 1 PN2C (N-SH) B LOOP RC INLET NOZZ TO SHELL AUG 1 Bl 1 om PRE B -D H2 281 1PN2D (IR) ISI/UT/ A-1 IS1 83.100 2B11 PN2D (IR) B LOOP RC INLET NOZZLE IR AUG 1 Bll om pRE B-D H2 281 1 PN2D (N-SH) ISI/UT/ A-1 IS1 83.90 281 1 PN2D (N-SH) B LOOP RC INLET NOZZ TO SHELL AUG 1 Bll om PRE B-D H2 281 1PN2E (IR) ISI/UT/ A-I IS1 83.100 2BllPN2E(IR)

B LOOP RC INLET NOZZLE IR AUG 1 Bll ow PRE B-D H2 281 1PN2E (N-SH) ISI/UT/ A-1 IS1 83.90 281 1 PN2E (N-SH) B LOOP RC INLET NOZZ TO SHELL AUG 1 Bll OWN PRE B-D HZ 281 1\2N2F (IR) ISIIUTI A-1 IS1 83.100 2B11PN2F (IR) A LOOP RC INLET NOZZLE IR AUG 1 B11 ow PRE B -D H2 281 1 PN2F (N-SH) ISI/UT/ A-1 IS1 83.90 281 1PN2F (N-SH) A LOOP RC INLET NOZZ TO SHELL AUG 1 Bll ow PRE B-D H2 281 1PN2G (IR) ISllUTl A-I IS1 83.100 281 1 PN2G (IR) A LOOP RC INLET NOZZLE IR AUG 1 B11 OWN PRE B-D H2 281 1PN2G (N-SH) ISI/UT/ A-1 IS1 83.90 281 1 PN2G (N-SH) A LOOP RC INLET NOZZ TO SHELL AUG 1 Bll OWN pRE N e-2 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - Q) o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - ~- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B -D H2 261 1PN2H (IR) ISIIUTI A-1 IS1 63.100 2811PN2H (IR) A LOOP RC INLET NOZZLE IR AUG 1 811 OWN PRE B -D H2 261 1UN2H (N-SH) ISIIUTI A-1 IS1 83.90 281 1PN2H (N-SH) 1 61 1 A LOOP RC INLET NOZZ TO SHELL AUG OWN Period 1 PRE B-D H2 281 1PN38 (IR) ISIIUTI A-1 IS1 83.100 2811PN3B (IR) 8 LOOP MS OUTLET NOZZLE IR AUG 1 61 1 OWN PRE PRE B -D H2 281 1UN2J (IR) ISIIUTI A-1 IS1 83.100 281 1 UN2J (IR) A LOOP RC INLET NOZZLE IR AUG 1 811 OWN PRE B-D H2 281 1PN2J (N-SH) ISIIUTI A-1 IS1 83.90 281 1UN2J (N-SH) A LOOP RC INLET NOZZ TO SHELL AUG 1 811 OWN PRE B-D H2 261 1UN2K (IR) ISIIUTI A- 1 IS1 83.100 261 1UN2K (IR) A LOOP RC INLET NOZZ IR AUG 1 811 OWN PRE B -D H2 281 1PN2K (N-SH) ISIIUTI A-1 IS1 83.90 2811PN2K (N-SH) A LOOP RC INLET NOZZ TO SHELL AUG 1 811 OWN PRE B -D H2 281 1PN3A (IR) ISllUTl A-1 IS1 63.100 2811PN3A(IR)

A LOOP MS OUTLET NOZZLE IR AUG 1 811 OWN PRE B -D H2 281 1UN3A (SH-N) ISIIUTI A-1 IS1 83.90 2811 UN3A (SH-N) A LOOP MS OUTLETSHELLTO NOZZ AUG 1 811 OWN - B -D H2 261 1 UN38 (SH-N) ISIIUTI A- 1 IS I 63.90 261 1PN3B (SH-N) 6 LOOP MS OUTLET SHELL TO NOZZ AUG 1 61 1 OWN PRE - - - - ---- -- -- ---- - - - - - - - - - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- Page 3 - 6 7H2R006 1 Period 2 Period 3 r 's P9 2 2 2 : I::

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1 HNP-2 Fourth Interval class 1 IS1 Plan Southern Nuclear Operating Company Page 4 - 6 711 2R006 1 Period 1 Period 2 Period 3 (Y C) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - -s-- - - - - - - - - - - - - F 2 5 -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. IternNO, Cornp. Desc. Class Summary 1 CornplD 1 System Scope I Method 1 Procedure Code Case B-D H2 281 1QN3C (IR) ISIIUTI A-1 IS1 B3.100 281 1QN3C (IR) C LOOP MS OUTLET NOZZLE IR AUG 1 B11 OWN pRE B -D H2 261 1 QN3C (SH-N) ISIIUTI A-1 IS1 83.90 281 1 QN3C (SH-N) CLOOPMSOUTLETSHELLTONOZZ AUG 1 Bll om PRE B -D H2 281 1 QN3D (IR) ISIIUTI A-1 IS1 83.1 00 281 1 QN3D (IR) D LOOP MS OUTLET NOZZLE IR AUG 1 B11 om PRE B -D H2 281 1QN3D (SH-N) ISllUTl A-1 IS1 B3.90 281 1 QN3D (SH-N) DLOOPMSOUTLETSHELLTONOZZ AUG 1 B11 om PRE B -D H2 2BllQN4A (IR) ISllUTl A-1 IS1 B3.100 2BllQN4A (IR) A-A LOOP FW INLET NOZZLE IR AUG 1 B11 om PRE B -D H2 2B11 QN4A (N-SH) ISllUTl A-1 IS1 83.90 281 1 QN4A (N-SH) A-ALOOPFWINLETNOZZTOSHELL AUG 1 B11 om PRE B -D H2 281 1QN4B (IR) ISllUTl A-1 IS1 B3.100 261 1 QN4B (IR) A-B LOOP FW INLET NOZZLE IR AUG 1 B11 om pRE B -D H2 281 1 QN4B (N-SH) ISlIUTl A-1 IS1 B3.90 281 1 QN4B (N-SH) A-8 LOOP FWINLETNOZZTOSHELL AUG 1 Bll om PRE B -D H2 281 1QN4C (IR) ISllUTl A-1 IS1 83.1 00 2B11QN4C (IR) B-C LOOP FW INLET NOZZLE IR AUG 1 B11 OWN pRE B -D H2 281 1\2N4C (N-SH) ISllUTl A-1 IS1 83.90 281 1 QN4C (N-SH) B-C LOOP FWINLETNOZZTOSHELL AUG 1 B11 OWN PRE m o E 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval class 1 IS1 Plan Southern Nuclear Operating Company Page 5 - 6 711212006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method 1 Procedure Code Case B -D H2 281 1UN4D (IR) ISIIUTI A-I IS1 83.100 281 1 UN4D (IR) B-D LOOP FW INLET NOZZLE IR AUG 1 Bll om pRE B-D H2 281 1 UN4D (N-SH) ISIIUTI A-1 IS1 83.90 281 1 UN4D (N-SH) 8-DLOOPFWINLETNOUTOSHELL AUG 1 Bll om PRE B-D H2 2B11 PNSA (IR) lSllUT1 A-1 IS1 83 100 281 1 UNSA (IR) A LOOP CS INLET NOZZLE IR AUG 1 Bll om PRE B-D H2 281 1UNSA (N-SH) ISIIUTI A-I IS1 83.90 281 1 UNSA (N-SH) A LOOP CS INLET NOU TO SHELL AUG 1 Bll om PRE B-D H2 281 1UNSB (IR) ISIIUTI A-1 IS1 83 100 281 1 UNSB (IR) B LOOP CS INLET NOZZLE IR AUG 1 Bll om PRE B-D H2 281 1 UNSB (N-SH) ISIIUTI A-1 IS1 83.90 281 1 UNSB (N-SH) B LOOP CS INLET NOZZ TO SHELL AUG 1 Bll om PRE B-D H2 281 1 UN6A (IR) ISINTI A-3 IS1 83.100 281 1 UN6A (IR) A LOOP RHR HS NOZZLE IR AUG 1 Bll om PRE B -D H2 281 1 UN6A (N-HEAD) ISIIUTI A-3 IS1 83 90 281 1 UN6A (N-HEAD) A LOOP RHR HS NOZZLTO HEAD AUG 1 Bll om PRE B -D H2 281 1UN6B (IR) ISINTI A-3 IS1 83 I00 281 1UN6B (IR) B LOOP RHR HS NOZZLE IR AUG 1 Bll om PRE B-D H2 281 1 UN6B (N-HEAD) ISIIUTI A-3 IS1 83 90 281 1PN6B (N-HEAD) B LOOP RHR HS NOZZ TO HEAD AUG 1 811 om PRE Q) o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - N- 2 2 5 5 -s-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - + - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope 1 Method I Procedure Code Case B -D H2 281 1QN7 (IR) ISlMI A-3 IS1 83.100 281 1QN7 (IR) MS VENT NOZZLE IR AUG 1 B11 OWN PRE B -D H2 281 1 QN7 (N) ISIIUTI A-3 IS1 83.90 281 1 QN7 (N) MS VENT NOZZLE AUG 1 81 1 OWN PRE B -D HZ 281 1 QN8A (IR) ISllUTl A-1 IS1 83.100 2BllQN8A (IR) A LOOP JP INSTR NOZZLE IR AUG 1 B11 OWN PRE B-D H2 281 1 QN8A (N-SH) lSllUT1 A-1 IS1 83.90 281 1 QN8A (N-SH) A LOOP JP INSTR NOZZ TO SHELL AUG 1 811 OWN PRE B-D H2 281 1 QN8B (IR) ISIIUTI A-1 IS1 83.100 281 1 QN8B (IR) B LOOP JP INSTR NOZZLE IR AUG 1 B11 OWN PRE B-D H2 281 1 QN88 (N-SH) ISIIUTI A-1 IS1 83.90 2B11QN8B (N-SH) B LOOP JP INSTR NOZZ TO SHELL AUG 1 B11 OWN PRE B -D H2 281 1QN9 (IR) ISIIUTI A-1 IS1 83.100 2811QN9 (IR) CRD INLET NOZZLE IR AUG 1 811 OWN PRE B -D H2 281 1 QN9 (N-SH) ISIIUTI A-1 IS1 83.90 2B11 QN9 (N-SH) CRD INLET NOZZ TO SHELL AUG 1 811 OWN Period 1 Page 6 - 6 711212006 1 Period 2 Period 3 d Revision:

1 HNP-2 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company d Page 1 - 1 711 712006 ( Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD /System Scope 1 Method I Procedure Code Case B -F H2 281 1 \1 INST-2A-1 ISIIPTI 2-BE-2 IS1 85.20 2B11\1 INST-2A-1 2N16A NOZZLE TO SAFE-END AIJG 1 B11 om PRE B -F H2 281 1 \1 INST-26-1 ISIIPTI 2-BE-2 IS1 85.20 261 1 \1 INST-2B-1 2N16B NOZZLE TO SAFE-END AIJG 1 Bl 1 om PRE B -F H2 2C41-1 SBLC-2-1 ISIIPTI 2-BE-3 IS1 85.20 2C41-1 SBLC-2-1 2N10 NOZZLE TO SAFE-END AIJG 1 C41 om PRE NP) 2 2 Fi Fi s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - m o 2 2 Fi Fi - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .? 2 5 - - - - - - - - - - - - - - - - ----s------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Period 1 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD /System Scope 1 Method 1 Procedure Code Case B-G-1 H2 281 IPNUT-1 ISINTINMP-ES-024201 A-33 IS1 B6 10 281 1 PNUT-1 CLOSURE HEAD NUTS AUG 1 Bll OWN PRE .- B-G-1 H2 281 1PNUT-10 ISIIVTINMP-ES-024-201 A-33 IS1 B6.10 281 1 PNUT-10 CLOSURE HEAD NUTS AUG 1 B11 OWN PRE B-G-1 H2 281 IPNUT-11 IS INTI A-33 IS1 B6.10 281 1 PNUT-11 CLOSUREHEADNUTS AUG 1 B11 OWN PRE - B-G-1 H2 281 1PNUT-12 ISIIVTI A-33 IS1 B6 10 2BllPNUT-12 CLOSUREHEADNUTS AUG 1 Bl 1 OWN PRE B-G-1 H2 2B11 PNUT-13 IS IIVTI A-33 IS1 B6 10 2BllPNUT-13 CLOSURE HEAD NUTS AUG 1 811 OWN PRE B-G-1 H2 281 1 QNUT-14 ISIIVTI A-33 IS1 B6 10 281 1 PNUT-14 CLOSURE HEAD NUTS AUG 1 B11 OWN PRE B-G-1 H2 281 1PNUT-15 ISIIVTI A-33 IS1 B6 10 281 1 PNUT-15 CLOSURE HEAD NUTS AUG 1 B11 OWN PRE 6-G-1 H2 281 1PNUT-16 ISliVTl A-33 IS1 B6 10 281 1 PNUT-16 CLOSUREHEADNUTS AUG 1 B11 OWN PRE B-G-1 H2 281 1PNUT-17 IS IIVTI A-33 IS1 86 10 2BllPNUT-17 CLOSURE HEAD NUTS AUG 1 B11 OWN PRE B-G-1 H2 281 1PNUT-18 ISIIVTI A-33 IS1 B6.10 2B1 IPNUT-18 CLOSURE HEAD NUTS AUG 1 811 OWN PRE 'age 1 - 27 Period 2 I Period 3 I::::

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 3 - 27 711 312006 ( Period 1 Period 2 Period 3 N r9 g 2 5 5 s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - . -s--- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD I System Scope 1 Method 1 Procedure Code Case B-G-1 H2 281 IQNUT-28 ISIMI A-33 IS1 B6 10 281 1 QNUT-28 CLOSURE HEAD NUTS AUG 1 Bll om PRE B-G-1 H2 281 1QNUT-29 ISINTI A-33 ISI B6.10 281 'IDNUT-29 CLOSURE HEAD NUTS AUG 1 B11 om PRE B-G-1 H2 281 1QNUT-3 ISIMINMP-ES-024-201 A-33 IS1 B6.10 2B11 QNUT-3 CLOSURE HEAD NUTS AUG 1 B11 om PRE B-G-1 H2 281 1QNUT-30 ISINTI A-33 IS1 B6.10 281 1 QNUT-30 CLOSURE HEAD NUTS AUG 1 B11 OWN PRE B-G-1 H2 281 1QNUT-31 IS IIVTI A-33 IS1 B6.10 281 1 QNUT-31 CLOSURE HEAD NUTS AUG 1 B11 om PRE BC-1 H2 281 1QNUT-32 ISIMI A-33 IS1 B6.10 281 1 QNUT-32 CLOSURE HEAD NUTS AUG 1 Bll OWN PRE B-G-1 H2 281 1 \2NUT-33 ISINTI A-33 IS1 B6.10 281 1 QNUT-33 CLOSURE HEAD NUTS AUG 1 B11 om PRE B-G-1 H2 281 1QNUT-34 ISINTI A-33 IS1 B6.10 281 1 QNUT-34 CLOSURE HEAD NUTS AUG 1 B11 om PRE B-G-1 H2 281 IQNUT-35 ISIIVTI A-33 IS1 B6.10 281 1QNUT-35 CLOSUREHEADNUTS AUG 1 B11 om PRE B-G-1 H2 281 1QNUT-36 ISIMI A-33 IS1 B6.10 2811 QNUT-36 CLOSURE HEAD NUTS AUG 1 B11 om pRE O) o z 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s----------- - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - ----- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company Category, ItemNO, lso No. Comp. Desc. Class Summary I CornplD I System Scope I Method I Procedure cod; case B-G-1 H2 281 1PNUT-37 ISIIVTI A-33 IS1 B6.10 261 1 PNUT-37 CLOSUREHEADNUTS AUG 1 a1 1 OWN PRE B-G-1 H2 281 1PNUT-38 ISllVTl A-33 IS1 B6.10 2BllPNUT-38 CLOSURE HEAD NUTS AUG 1 B1 1 OWN PRE B-G-1 H2 281 1PNUT-39 ISllVTl A-33 IS1 66.10 2BllPNUT-39 CLOSURE HEAD NUTS AUG 1 B1 1 OWN PRE B-G-1 H2 281 1PNUT-4 ISIIVTINMP-ES-024-201 A-33 IS1 B6.10 2B11 PNUT-4 CLOSURE HEAD NUTS AUG 1 B11 OWN PRE B-G-1 H2 201 1PNUT-40 ISllVTl A-33 IS1 B6 10 281 1 PNUT-40 CLOSURE HEAD NUTS AUG 1 81 1 OWN PRE B-G-1 H2 281 1PNUT-41 ISINTINMP-ES-024-201 A-33 IS1 B6 10 2B11 PNUT-41 CLOSURE HEAD NUTS AUG 1 01 1 OWN PRE B-G-1 H2 281 1 PNUT-42 ISllVTINMP-ES-024-201 A-33 1st B6.10 2B11 PNUT-42 CLOSURE HEAD NUTS AUG 1 a1 1 OWN PRE B-G-1 H2 261 1PNUT-43 ISINTINMP-ES-024-201 A-33 IS1 06.10 281 1 PNUT-43 CLOSURE HEAD NUTS AUG 1 Bll OWN PRE B-G-1 H2 281 1PNUT-44 ISIIVTINMP-ES-024-201 A-33 IS1 B6.10 2B11 PNUT-44 CLOSURE HEAD NUTS AUG 1 a1 1 OWN PRE B-G-1 H2 281 1PNUT-45 ISINTINMP-ES-024-201 A-33 IS1 B6 10 281 1PNUT-45 CLOSURE HEAD NUTS AUG 1 81 1 OWN PRE Page 4 - 27 Period 1 Period 2 Period 3 I Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 5 - 27 711 312006 1 Period 1 Period 2 Period 3 N ~3 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B-G-1 H2 2BllPNUT-46 ISllVTINMP-ES-024201 A-33 IS1 B6.10 281 1 PNUT-46 CLOSURE HEAD NUTS AUG 1 Bll om PRE B-G-1 H2 281 1PNUT-47 ISllVTINMP-ES-024201 A-33 IS1 B6.10 281 1 PNUT-47 CLOSURE HEAD NUTS AUG 1 B11 om PRE B-G-I H2 281 1PNUT-48 ISllVTINM P-ES-024-201 A-33 IS1 B6.10 281 1 PNUT-48 CLOSURE HEAD NUTS AUG 1 Bll om PRE B-G-1 H2 281 1 PNUT-49 ISllVTINMP-ES-024201 A-33 IS1 B6.10 281 1 PNUT-49 CLOSURE HEAD NUTS AUG 1 Bll om PRE B-G-1 H2 281 1PNUT-5 ISllVTINMP-ES-024-201 A-33 IS1 B6.10 281 1 PNUT-5 CLOSURE HEAD NUTS AUG 1 Bl I om PRE B-G-1 H2 281 1PNUT-50 ISllVTINMP-ES-024201 A-33 IS1 B6.10 2811 PNUT-50 CLOSURE HEAD NUTS AUG 1 Bll om PRE B-G-I H2 281 1PNUT-51 ISllVTINMP-ES-024-201 A-33 IS1 B6.10 281 1 PNUT-51 CLOSURE HEAD NUTS AUG 1 81 1 om PRE B-G-1 H2 281 1PNUT-52 ISINTINMP-ES-024201 A-33 IS1 B6.10 281 1 PNUT-52 CLOSURE HEAD NUTS AUG 1 Bll om PRE B-G-1 H2 2B11 PNUT-53 ISllVTINMP-ES-024201 A-33 IS1 B6.10 2BllPNUT-53 CLOSURE HEAD NUTS AUG 1 B11 om PRE B-G-1 H2 281 1 PNUT-54 ISINTINMP-ES-024201 A-33 IS1 B6.10 281 1PNUT-54 CLOSURE HEAD NUTS AUG 1 Bll om PRE Q) o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - . s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope I Method I Procedure Code Case B-G-1 HZ 281 1PNUT-55 ISIMINMP-ES-024-201 A-33 IS1 86 10 281 1 PNUT-55 CLOSURE HEAD NUTS AUG 1 Bll OWN PRE B-G-1 HZ 281 1PNUT-56 ISIMINMP-ES-024-201 A-33 IS1 B6 10 281 1 PNUT-56 CLOSURE HEAD NUTS AUG 1 81 1 OWN PRE B-G-1 HZ 281 1PNUT-6 ISINTINMP-ES-024-201 A-33 IS1 86 10 2BllPNUT-6 CLOSURE HEAD NUTS AUG 1 B11 OWN PRE B-G-1 HZ 281 1PNUT-7 l S IlVTl A-33 IS1 86 10 281 1 PNUT-7 CLOSURE HEAD NUTS AUG 1 B11 OWN PRE B-G-I HZ 281 1PNUT-8 ISIIVTI A-33 IS1 B6 10 2BllPNUT-8 CLOSURE HEAD NUTS AUG 1 Bll OWN PRE B-G-1 HZ 281 1 PNUT-9 ISIMI A-33 IS1 86 10 2BllPNUT-9 CLOSUREHEADNUTS AUG 1 81 1 OWN PRE B-G-1 HZ 2B31PRC-A PUMP BOLT-1 IS1 86 180 2B31PRC-A PUMP BOLT-1 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 HZ 2B31PRC-A PUMP BOLT-1 0 IS1 86 180 2B31PRC-A PUMP BOLT-10 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 H2 2831PRC-A PUMP BOLT-11 IS1 86 180 2831 PRC-A PUMP BOLT-11 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 HZ 2831PRC-A PUMP BOLT-12 IS1 86 180 2831 PRC-A PUMP BOLT-12 PUMP BOLTING AUG 1 83 1 OWN PRE Period 1 'age 6 - 27 Period 2 I Period 3 I Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 7 - 27 7/13/2006 1 Period 1 Period 2 Period 3 Category, Iso NO. ItemNO, Comp. Desc.

Class ~urnniary I ComplD I System Scope I Method I Procedure Code Case B-G-1 H2 2B31PRC-A PUMP BOLT-1 3 IS1 86 180 2831 PRC-A PUMP BOLT-13 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 H2 2B31PRC-A PUMP BOLT-14 IS1 86.180 2B31PRC-A PUMP BOLT-14 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 H2 2B31PRC-A PUMP BOLT-15 IS1 86.180 2B31PRC-A PUMP BOLT-15 PUMP BOLTING AUG 1 83 1 om PRE BC-1 H2 2B31PRC-A PUMP BOLT-16 IS1 86.180 2B31PRC-A PUMP BOLT-16 PUMP BOLTING AUG 1 831 om PRE B-G-1 H2 2B31PRC-A PUMP BOLT-2 IS1 B6.180 2B31PRC-A PUMP BOLT-2 PUMP BOLTING AUG 1 B3 1 om PRE B-G-1 H2 2B31PRC-A PUMP BOLT-3 IS1 86.180 2B31PRC-A PUMP BOLT-3 PUMP BOLTING AUG 1 831 om PRE B-G-1 H2 2B31PRC-A PUMP BOLT-4 IS1 B6.180 2B31PRC-A PUMP BOLT-4 PUMP BOLTING AUG 1 B3 1 om PRE BC-1 H2 2B31PRC-A PUMP BOLT-5 IS1 86.180 2B31PRC-A PUMP BOLT-5 PUMP BOLTING AUG 1 831 om PRE B-G-1 H2 2B31PRC-A PUMP BOLT-6 IS1 B6.180 2B31PRC-A PUMP BOLT-6 PUMP BOLTING AUG 1 83 1 OWN PRE B-G-1 H2 2B31PRC-A PUMP BOLT-7 IS1 B6.180 2B31PRC-A PUMP BOLT-7 PUMP BOLTING AUG 1 B3 1 om PRE m o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - F 2 5 ------------ - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -----..------ - - - - - - - - ------------ - - - - -------- - - - - C( D 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - - - - - ---- - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 8 - 27 711 312006 1 Period 1 Period 2 Period 3 N P) 2 2 ?i 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Cornp. Desc.

Class Summary 1 CornplD 1 System Scope I Method I Procedure Code Case B-G-1 H2 2B31PRC-A PUMP BOLT-8 IS1 86 180 2B31PRC-A PUMP BOLT-8 PUMP BOLTING AUG 1 831 OWN PRE BC-1 H2 2B31PRC-A PUMP BOLT-9 IS1 86.180 2B31PRC-A PUMP BOLT-9 PUMP BOLTING AUG 1 831 om PRE 6-G-1 H2 2B31PRC-B PUMP BOLT-1 ISllUTl IS1 86.180 2B31PRC-B PUMP BOLT-1 PUMP BOLTING AUG 1 831 om PRE B-G-1 H2 2B31PRC-B PUMP BOLT-1 0 ISIIUTI IS1 B6.180 2B31 PRC-B PUMP BOLT-1 0 PUMP BOLTING AUG 1 83 1 om PRE B-G-1 H2 2B31PRC-B PUMP BOLT-1 1 ISIIUTI IS1 86.180 2B31PRC-B PUMP BOLT-1 1 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 H2 2B31PRC-B PUMP BOLT-1 2 ISIIUTI IS1 86.180 2B31PRC-B PUMP BOLT-12 PUMP BOLTING AUG 1 83 1 OWN PRE B-G-1 H2 2831 PRC-B PUMP BOLT-1 3 ISIIUTI IS1 B6.180 2B31PRC-B PUMP BOLT-13 PUMP BOLTING AUG 1 83 1 om pRE BC-1 H2 2B31PRC-B PUMP BOLT-1 4 ISIIUTI IS1 86.180 2B31PRC-B PUMP BOLT-14 PUMP BOLTING AUG 1 B31 om PRE B-G-1 H2 2831 PRC-B PUMP BOLT-1 5 ISIIUTI IS1 86.180 2B31PRC-B PUMP BOLT-15 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 H2 2831 PRC-B PUMP BOLT-1 6 ISIIUTI IS1 86 180 2B31PRC-B PUMP BOLT-16 PUMP BOLTING AUG 1 831 OWN PRE m o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----s------- - - - - - - - - - - - - S - - - - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----S------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------ - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 9 - 27 711 312006 1 Period 1 Period 2 Period 3 (Y m 2 2 5 5 - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method I Procedure Code Case 0-G-1 H2 2B31PRC-B PUMP BOLT-2 ISIIUTI IS1 86 180 2831 PRC-B PUMP BOLT-2 PUMP BOLTING AUG 1 83 1 om PRE B-G-I H2 2B31PRC-B PUMP BOLT-3 ISIIUTI IS1 86 180 2831 PRC-B PUMP BOLT-3 PUMP BOLTING AUG 1 83 1 om PRE 6-G-I H2 2B31PRC-B PUMP BOLT-4 ISIIUTI IS1 86 180 2831 PRC-B PUMP BOLT-4 PUMP BOLTING AUG 1 831 OWN pRE 6-G-1 H2 2B31PRC-B PUMP BOLT-5 ISIIUTI IS1 86 180 2B31PRC-B PUMP BOLT-5 PUMP BOLTING AUG 1 83 1 OWN PRE 0-G-1 H2 2B31PRC-B PUMP BOLT-6 ISIIUTI IS1 86 180 2831 PRC-B PUMP BOLT-6 PUMP BOLTING AUG 1 83 1 OWN PRE 6-G-I H2 2B31PRC-B PUMP BOLT-7 ISIIUTI IS1 B6.180 2831 PRC-B PUMP BOLT-7 PUMP BOLTING AUG 1 831 OWN pRE 6-G-I H2 2B31PRC-B PUMP BOLT8 ISIIUTI IS1 86 180 2B31QRC-B PUMP BOLT-8 PUMP BOLTING AUG 1 83 1 OWN PRE 0-G-1 H2 2B31PRC-B PUMP BOLT-9 ISIIUTI IS1 86 180 2831PRC-B PUMP BOLT-9 PUMP BOLTING AUG 1 83 1 om PRE 6-G-1 H2 2B31PRC-A PUMP-FLANGE IS1 86 190 2B31PRC-A PUMP-FLANGE FLANGE SURFACE AUG 1 83 1 OWN PRE 6-G-1 H2 2B31PRC-B PUMP-FLANGE IS1 86 190 2B31PRC-B PUMP-FLANGE FLANGE SURFACE AUG 1 83 1 OWN PRE o E 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - y 2 5 ----s------- - - - - - - - - - - - - ----s------- - - - - --------- - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - s - - - - - - - - - - - - - - - ----s------- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-1 H2 281 1PSTUD-1 ISllUTlNMP-ES-024504 A-33 IS1 86.20 281 1 PSTUD-1 CLOSURE HEAD STUDS AUG 1 81 1 OWN PRE B-G-1 H2 281 1PSTUD-10 ISIIUTI A-33 IS1 86.20 281 1 PSTUD-1 0 CLOSURE HEAD STUDS AUG 1 81 1 OWN PRE B-G-1 H2 281 1PSTUD-11 ISIIUTI A-33 IS1 86.20 281 1 PSTUD-11 CLOSURE HEAD STUDS AUG 1 81 1 OWN PRE B-G-1 H2 281 1QSTUD-12 lSllUT1 A-33 IS1 86.20 281 1 PSTUD-12 CLOSURE HEAD STUDS AUG 1 811 OWN PRE B-G-1 H2 281 1PSTUD-13 ISIIUTI A-33 IS1 86.20 281 1 PSTUD-13 CLOSURE HEAD STUDS AUG 1 811 OWN PRE B-G-1 H2 281 1PSTUD-14 ISIIUTI A-33 IS1 86.20 281 1 PSTUD-14 CLOSURE HEAD STUDS AUG 1 81 1 OWN PRE B-G-1 H2 281 1PSTUD-15 ISllUTl A-33 IS1 86.20 281 1 PSTUD-15 CLOSURE HEAD STUDS AUG 1 Bll OWN PRE B-G-1 H2 281 1PSTUD-1 6 ISIIUTI A-33 IS1 86.20 281 1PSTUD-16 CLOSURE HEAD STUDS AUG 1 81 1 OWN PRE B-G-1 H2 281 1 PSTUD-17 lSllUT1 A-33 IS1 86.20 281 1 PSTUD-17 CLOSURE HEAD STUDS AUG 1 81 1 OWN PRE B-G-1 H2 281 1PSTUD-18 ISIIUTI A-33 IS1 86.20 281 IQSTUD-18 CLOSURE HEAD STUDS AUG 1 81 1 OWN PRE Page 10 - 27 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 1 - 27 7/13/2006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case 0-G-1 H2 281 IDSTUD-19 lSllUT1 A-33 IS1 86.20 281 1 PSTUD-19 CLOSURE HEAD STUDS AUG 1 811 ow PRE 0-G-1 H2 281 1 DSTUD-2 ISllUTlNMP-ES-024504 A-33 IS1 86.20 281 1 DSTUD-2 CLOSUREHEADSTUDS AUG 1 B11 ow PRE 0-G-1 H2 281 1 DSTUD-20 lSllUT1 A-33 IS1 86.20 281 1 DSTUD-20 CLOSURE HEAD STUDS AUG 1 81 1 ow PRE 0-G-I H2 281 IDSTUD-21 ISllUTl A-33 IS1 86.20 281 1 DSTUD-21 CLOSUREHEADSTUDS AUG 1 B11 ow PRE 0-G-I H2 281 IDSTUD-22 ISIIUTI A-33 IS1 86.20 281 IDSTUD-22 CLOSUREHEADSTUDS AUG 1 81 1 ow PRE 04-1 H2 281 IDSTUD-23 ISllUTl A-33 IS1 86.20 281 IDSTUD-23 CLOSURE HEAD STUDS AUG 1 81 1 ow PRE 0-G-1 H2 281 IDSTUD-24 ISIIUTI A-33 IS1 86.20 281 1 PSTUD-24 CLOSURE HEAD STUDS AUG 1 81 1 ow PRE 0-G-I H2 281 1 DSTUD-25 ISIIUTI A-33 IS1 86.20 281 1 PSTUD-25 CLOSURE HEAD STUDS AUG 1 Bl 1 ow PRE 04-1 H2 281 IDSTUD-26 lSllUT1 A-33 IS1 86.20 281 1 DSTUD-26 CLOSURE HEAD STUDS AUG 1 Bll OWN PRE H2 281 1 DSTUD-27 lSllUT1 A-33 IS1 0-G-1 66.20 281 1 PSTUD-27 CLOSURE HEAD STUDS AUG 1 B11 ow PRE r 2 5 ----s------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - --------- - - - - m o 5 2 5 5 - - - - - - - - - - - - - - - - - - - - - ~- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - e4 m 2 2 5 % - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - --- - - - -

J Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 12- 27 Period I Period 2 7H312006 1 Period 3 N o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary 1 ComplD 1 System Scope I Method I Procedure Code Case B-G-1 H2 281 IDSTUD-28 ISllUTl A-33 IS1 86.20 281 1 DSTUD-28 CLOSURE HEAD STUDS AUG 1 811 om pRE B-G-1 H2 281 1 DSTUD-29 ISIIUTI A-33 IS1 B6 20 281 1PSTUD-29 CLOSURE HEAD STUDS AUG 1 Bl 1 om PRE B-G-1 H2 2B1 IDSTUD-3 ISllUTlNMP-ES-024-504 A-33 IS1 86.20 281 1 DSTUD-3 CLOSURE HEAD STUDS AUG 1 811 om PRE B-G-1 H2 281 IDSTUD-30 ISIIUTI A-33 IS1 86.20 281 1 DSTUD-30 CLOSURE HEAD STUDS AUG 1 Bll om PRE B-G-1 H2 281 IDSTUD-31 ISIIUTI A-33 IS1 86.20 2811 DSTUD-31 CLOSURE HEAD STUDS AUG 1 811 om PRE B-G-1 H2 281 1 DSTUD-32 ISIIUTI A-33 IS1 86.20 2811 DSTUD-32 CLOSURE HEAD STUDS AUG 1 811 om PRE B-G-1 H2 281 1 DSTUD-33 lSllUT1 A-33 IS1 86.20 2811 DSTUD-33 CLOSURE HEAD STUDS AUG 1 811 om PRE B-G-1 H2 281 1 DSTUD-34 lSllUT1 A-33 IS1 86.20 281 1 DSTUD-34 CLOSURE HEAD STUDS AUG 1 B11 om PRE B-G-1 H2 281 IDSTUD-35 lSllUT1 A-33 IS1 86.20 281 IDSTUD-35 CLOSURE HEAD STUDS AUG 1 811 om PRE B-G-1 H2 281 1 DSTUD-36 lSllUT1 A-33 IS1 86.20 281 1 PSTUD-36 CLOSURE HEAD STUDS AUG 1 811 om PRE a o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - <------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - F 2 5 ---.----s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - s----------- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 13 - 27 711312006 1 Period 1 Period 2 Period 3 N- 2 2 5 5 -s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - --- - - - - -S--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - --- - - - - r 2 i5 - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - s----------- - - - - --------- - - - - - - - - - - - - - - - - - - - s----------- - - - - - - - - - - - - S----------- - - - - - - - - - - - - s----------- - - - - --------- - - - - s----------- - - - - - - - - - - - - s---------- - - - - --------- - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope 1 Method 1 Procedure Code Case B-G-I H2 281 1USTUD-37 ISIIUTI A-33 IS1 B6 20 281 1 USTUD-37 CLOSURE HEAD STUDS AUG 1 B11 om PRE B-G-1 H2 281 1USTUD-38 ISIIUTI A-33 IS1 86.20 2B11 USTUD-38 CLOSURE HEAD STUDS AUG 1 Bll om PRE B-G-1 H2 281 1\2STUD-39 ISIIUTI A33 IS1 86.20 2B11 USTUD-39 CLOSURE HEAD STUDS AUG 1 81 1 om PRE B-G-1 H2 281 1 USTUD-4 ISllUTINMP-ES-024-504 A-33 IS1 86.20 2B11 USTUD-4 CLOSURE HEAD STUDS AUG 1 Bll om PRE B -G-1 H2 281 1USTUD-40 ISIIUTI A-33 IS1 86.20 281 1 USTUD-40 CLOSUREHEADSTUDS AUG 1 Bll om PRE B-G-I H2 281 1 USTUD-41 ISIIUTINMP-ES-024-504 A-33 IS1 B6 20 2B11 USTUD-41 CLOSUREHEADSTUDS AUG 1 Bll om PRE B-G-1 H2 281 1USTUD-42 ISIIUTINMP-ES-024-504 A-33 IS1 86.20 2B11 USTUD-42 CLOSURE HEAD STUDS AUG 1 Bll om PRE B-G-1 H2 281 1USTUD-43 ISIIUTINMP-ES-024-504 A-33 IS1 86.20 281 1 USTUD-43 CLOSURE HEAD STUDS AUG 1 Bl 1 om PRE B-G-I H2 281 1 USTUD-44 ISIIUTINMP-ES-024-504 A-33 IS1 86 20 2 B 1 1 USTU D-44 CLOSUREHEADSTUDS AUG 1 B11 om PRE B-G-1 H2 281 1USTUD-45 ISllUTlNMP-ES-024-504 A-33 IS1 B6 20 281 1 USTUD-45 CLOSURE HEAD STUDS AUG 1 B11 om PRE Q) o 2 2 5 5 ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 Category, ItemNO, HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary I ComplD 1 System Scope 1 Method I Procedure Code Case B-G-1 H2 281 IPSTUD-46 ISIIUTINMP-ES-024504 A-33 IS1 86 20 2B11 PSTUD-46 CLOSURE HEAD STUDS AUG 1 B11 OWN PRE B-G-1 H2 281 IPSTUD-47 ISIIUTINMP-ES-024-504 A-33 IS1 86.20 281 1 PSTUD-47 CLOSURE HEAD STUDS AUG 1 81 I OWN PRE B-G-1 H2 281 1 PSTUD-48 ISllUTINMP-ES-024504 A-33 IS1 86.20 281 1 PSTUD-48 CLOSURE HEAD STUDS AUG 1 Bl I OWN PRE B-G-1 H2 281 1 PSTUD-49 ISIIUTINMP-ES-024-504 A-33 IS1 B6 20 281 1 PSTUD-49 CLOSURE HEAD STUDS AUG 1 811 OWN PRE B-G-1 H2 281 1PSTUD-5 ISIIUTINMP-ES-024-504 A-33 IS1 86.20 281 1 PSTUD-5 CLOSUREHEADSTUDS AUG 1 B11 OWN PRE B-G-1 H2 281 1 PSTUD-50 ISIIUTINMP-ES-024504 A-33 IS1 86.20 281 IPSTUD-50 CLOSURE HEAD STUDS AUG 1 811 OWN PRE B-G-1 H2 281 1 PSTUD-51 ISIIUTINMP-ES-024504 A-33 IS1 86 20 281 IPSTUD-51 CLOSURE HEAD STUDS AUG 1 Bl I OWN PRE B-G-1 H2 281 IPSTUD-52 ISIIUTINMP-ES-024504 A-33 IS1 86.20 281 1 PSTUD-52 CLOSURE HEAD STUDS AUG 1 B11 OWN PRE B-G-1 H2 281 1 QSTUD-53 ISIIUTINMP-ES-024-504 A-33 IS1 86 20 281 1 PSTUD-53 CLOSURE HEAD STUDS AUG 1 Bll OWN PRE B-G-1 H2 281 1 PSTUD-54 ISIIUTINMP-ES-024504 A-33 IS1 86.20 281 1 PSTUD-54 CLOSURE HEAD STUDS AUG 1 81 I OWN PRE Page 14- 27 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 15 - 27 711 312006 1 Period 1 Period 2 Period 3 N ~3 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - tt-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - . - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD 1 System Scope 1 Method 1 Procedure Code Case B-G-1 H2 281 1 PSTUD-55 ISllUTINMP-ES-024504 A-33 IS1 86.20 281 1 PSTUD-55 CLOSURE HEAD STUDS AUG 1 81 1 om PRE B-G-1 H2 281 1PSTUD-56 ISllUTlNMP-ES-024504 A-33 IS1 86.20 281 1 PSTUD-56 CLOSURE HEAD STUDS AUG 1 81 1 om PRE B-G-1 H2 281 1 PSTUD-6 ISllUTINMP-ES-024504 A-33 IS1 86.20 281 1 PSTUD-6 CLOSUREHEADSTUDS AUG 1 811 om PRE B-G-1 H2 281 1 PSTUD-7 ISllUTl A-33 IS1 86.20 2811PSTUD-7 CLOSURE HEAD STUDS AUG 1 811 OWN PRE B-G-1 H2 281 1PSTUD-8 ISIIUTI A-33 IS1 86.20 281 1 PSTUD-8 CLOSURE HEAD STUDS AUG 1 81 1 OWN PRE B-G-1 H2 281 1 PSTUD-9 ISIIUTI A-33 IS1 86.20 281 1 PSTUD-9 CLOSUREHEADSTUDS AUG 1 81 1 OWN PRE B-G-1 H2 2831PRC-A PUMP-NUTS IS1 86.200 2831 PRC-A PUMP-NUTS RC PUMP A NUTS AUG 1 831 OWN PRE B-G-1 H2 2831PRC-8 PUMP-NUTS IS1 86.200 2831PRC-8 PUMP-NUTS RC PUMP 8 NUTS AUG 1 83 1 om PRE B-G-1 H2 281 1PLIG-1 ISllUTINMP-ES-024504 A-33 IS1 86.40 281 1 PLIG-1 FLANGE LIGAMENTS AUG 1 81 1 OWN PRE B-G-1 H2 281 1 PLIG-10 ISIIUTI A-33 IS1 86 40 281 IPLIG-10 FLANGE LIGAMENTS AUG 1 81 1 OWN PRE o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - tt-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - F 2 5 s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - t--- - - - - - - - - - - - - tt--t---tt-- - - - - - - - - - - - - s--------.-- - - - - - - - - - - - - ----s------- - - - - - - - - - - - -

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1 Category, IternNO, Class Surnrnarv I Corn~lD I Svstern HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Cornp. Desc. Sco~e I Method I Procedure Code Case B-G-1 H2 281 1PLIG-11 ISIIUTI A-33 IS1 86.40 2BllQLIG-11 FLANGE LIGAMENTS AUG 1 81 1 OWN PRE B-G-1 H2 281 1 QLIG-12 ISIIUTI A-33 IS1 B6.40 2B11 PLIG-12 FLANGE LIGAMENTS AUG 1 B11 OWN PRE B-G-1 H2 2B11 QLIG-13 lSllUT1 A-33 IS1 86.40 2B11 PLIG-13 FLANGE LIGAMENTS AUG 1 B11 OWN PRE B-G-I H2 281 1QLIG-14 ISIIUTI A-33 IS1 86.40 281 1QLIG-14 FLANGE LIGAMENTS AUG 1 Bll OWN PRE B-G-1 H2 281 1QLIG-15 ISIIUTI A-33 IS1 86.40 2B1 IQLIG-15 FLANGE LIGAMENTS AUG 1 B11 OWN PRE B-G-I H2 281 1QLIG-16 ISllUTl A-33 IS1 B6.40 2B1 IPLIG-16 FLANGE LIGAMENTS AUG 1 81 1 OWN PRE B-G-I H2 281 1QLIG-17 ISIIUTI A-33 IS1 86.40 2B11 QLIG-17 FLANGE LIGAMENTS AUG 1 Bl I OWN PRE B-G-I H2 281 1QLIG-18 ISIIUTI A-33 IS1 86.40 2B11 QLIG-18 FLANGE LIGAMENTS AUG 1 Bl 1 OWN PRE B-G-I H2 281 1QLIG-19 lSllUT1 A-33 IS1 86.40 2BllQLIG-19 FLANGE LIGAMENTS AUG 1 B11 OWN PRE B-G-I H2 2B11 QLIG-2 ISIIUTINMP-ES-024504 A-33 IS1 B6.40 281 1 PLIG-2 FLANGE LIGAMENTS AUG 1 B11 OWN PRE Page 16 - 27 Period 1 Period 2 Period 3 I Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 17 - 27 Period 1 Period 2 711312006 1 Period 3 (Y P? 2 2 5 I, - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - -s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - S--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - --- - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope I Method I Procedure Code Case B-G-1 H2 281 1 PLIG-20 ISIIUTI A-33 IS1 B6 40 2B11 ULIG-20 FLANGE LIGAMENTS AUG 1 Bll om PRE B-G-1 H2 281 1 ULIG-21 ISIIUTI A-33 IS1 B6 40 2B11 PLIG-21 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-1 H2 281 IPLIG-22 lSllUT1 A-33 IS1 B6 40 2B11 PLIG-22 FLANGE LIGAMENTS AUG 1 B11 OWN PRE B-G-1 H2 281 1 PLIG-23 lSllUT1 A-33 1SI B6 40 2B11 PLIG-23 FLANGE LIGAMENTS AUG 1 Bl I om PRE B-G-1 H2 281 1 ULIG-24 ISIIUTI A-33 IS1 86.40 2B1 IPLIG-24 FLANGE LIGAMENTS AUG 1 Bl I om pRE B-G-1 H2 281 1 PLIG-25 ISIIUTI A-33 IS1 B6 40 281 1 PLIG-25 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-1 H2 281 1 ULIG-26 ISIIUTI A-33 IS1 B6 40 201 1 PLIG-26 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-1 H2 281 1 PLIG-27 lSllUT1 A-33 IS1 66 40 201 IPLIG-27 FLANGE LIGAMENTS AUG 1 81 1 om PRE B-G-1 H2 281 1 PLIG-28 ISIIUTI A-33 IS1 B6.40 2B11 PLIG-28 FLANGE LIGAMENTS AUG 1 81 1 om PRE B-G-1 H2 281 1 ULIG-29 lSllUT1 A-33 IS1 B6 40 201 IDLIG-29 FLANGE LIGAMENTS AUG 1 Bll om PRE a, o E 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -? 2 I, ----s------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - -------- - - - - --------- - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 18 - 27 711 312006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B-G-I H2 2BllQLIG-3 ISllUTINMP-ES-024-504 A-33 IS1 86 40 281 1 QLIG-3 FLANGE LIGAMENTS AUG 1 81 1 om PRE B-G-I H2 281 1QLIG-30 ISIIUTI A-33 IS1 B6.40 2B1 1QLIG-30 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-I H2 281 1 QLIG-31 lSllUT1 A-33 IS1 86 40 2B1 IQLIG-31 FLANGE LIGAMENTS AUG 1 Bl I om PRE B-G-I H2 281 IQLIG-32 ISIIUTI A-33 IS1 86.40 2B1 IQLIG-32 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-I H2 281 1 QLIG-33 lSllUT1 A-33 IS1 B6.40 2B11 QLIG-33 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-1 H2 281 1 QLIG-34 ISIIUTI A-33 IS1 86.40 2B11 QLIG-34 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-I H2 281 1 QLIG-35 ISllUTl A-33 IS1 86.40 2B11 QLIG-35 FLANGE LIGAMENTS AIJG 1 B11 om PRE B-G-I H2 281 1 QLIG-36 ISIIUTI A-33 IS1 86.40 2B1 IQLIG-36 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-I H2 281 1 QLIG-37 ISIIUTI A-33 IS1 86.40 2B11 QLIG-37 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-1 H2 2B1 IQLIG-38 ISllUTl A-33 ISI 86.40 2B11\2LIG-38 FLANGE LIGAMENTS AUG 1 B11 om PRE N P) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - -s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - -s--- - - - - - - - - - - - - -S--- - - - - - - - - - - - - m o z 2 F4 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - F 2 2 s----------- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 19 - 27 711312006 1 Period 1 Period 2 Period 3 CY P) 2 2 5 z s--- - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Cornp. Desc. Class Summary I CornplD I System Scope I Method I Procedure Code Case B-G-1 H2 281 1 ULIG-39 ISIIUTI A-33 IS1 B6 40 2BllQLIG-39 FLANGE LIGAMENTS AUG 1 B11 ow PRE B-G-1 H2 281 1ULIG-4 ISIIUTINMP-ES-024-504 A-33 IS1 B6 40 281 1 QLIG-4 FLANGE LIGAMENTS AUG 1 B11 ow PRE B-G-1 H2 281 1 ULIG-40 ISIIUTI A-33 IS1 B6 40 2B11 ULIG-40 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-1 H2 281 1ULIG-41 ISIIUTINMP-ES-024-504 A-33 IS1 B6 40 2B11 ULIG-41 FLANGE LIGAMENTS AUG 1 B11 ow PRE B-G-1 H2 281 1 ULIG-42 ISIIUTINMP-ES-024-504 A-33 IS1 B6 40 2B11 ULIG-42 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-1 H2 281 1ULIG-43 ISIIUTINMP-ES-024-504 A-33 IS1 B6 40 281 1 ULIG-43 FLANGE LIGAMENTS AUG 1 Bll om PRE B-G-1 H2 281 1ULIG-44 ISllUTINMP-ES-024-504 A-33 IS1 B6 40 2BllULIG-44 FLANGE LIGAMENTS AUG 1 Bll ow PRE B-G-1 H2 281 1 ULIG-45 ISIIUTINM P-ES-024-504 A-33 IS1 B6 40 281 1 ULIG-45 FLANGE LIGAMENTS AUG 1 B11 ow PRE B-G-1 H2 281 1ULIG-46 ISIIUTINMP-ES-024-504 A-33 IS1 B6 40 2B11 ULIG-46 FLANGE LIGAMENTS AUG 1 B11 ow PRE 6-G-1 H2 281 1ULIG-47 ISIIUTINMP-ES-024-504 A-33 IS1 B6 40 2BllULIG-47 FLANGE LIGAMENTS AUG 1 B11 ow PRE m o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 - - - - - - - - - - - - - - - - s----------- - - - - - - - - - - - - - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 20 - 27 7/13/2006 1 Period 1 Period 2 Period 3 N P) 2 2 I, 5 - - - - --- - - - - - - - - ---- - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - Category, lso No. IternNO, ~omp. Desc. Class Summary I ComplD I System Scope 1 Method 1 Procedure Code Case B-G-1 H2 281 1QLIG-48 ISllUTINMP-ES-024504 A-33 IS1 B6 40 2B11 VLIG-48 FLANGE LIGAMENTS AUG 1 B1 1 om PRE B-G-1 H2 281 1QLIG-49 ISllUTINMP-ES-024504 A-33 IS1 B6 40 2B11 QLIG-49 FLANGE LIGAMENTS AUG 1 B1 1 om PRE B-G-1 H2 281 IQLIG-5 ISllUTINMP-ES-024-504 A-33 IS1 B6 40 2B11 QLIG-5 FLANGE LIGAMENTS AUG 1 B1 1 om PRE B-G-1 H2 281 1QLIG-50 ISIIUTINMP-ES-024-504 A-33 IS1 B6 40 201 1 QLIG-50 FLANGE LIGAMENTS AUG 1 B1 1 OWN PRE B-G-1 H2 281 1 QLIG-51 ISIIUTINMP-ES-024504 A-33 IS1 B6 40 2B11 QLIG-51 FLANGE LIGAMENTS AUG 1 B1 1 om PRE B-G-1 H2 281 IQLIG-52 ISllUTlNMP-ES-024504 A-33 IS1 B6 40 2B11 QLIG-52 FLANGE LIGAMENTS AUG 1 B1 1 om PRE B-G-1 H2 281 1QLIG-53 ISIIUTINMP-ES-024-504 A-33 IS1 B6 40 2B11 QLIG-53 FLANGE LIGAMENTS AIJG 1 B1 1 OWN PRE B-G-1 H2 281 1 QLIG-54 ISllUTlNMP-ES-024504 A-33 IS1 B6 40 2B11 QLIG-54 FLANGE LIGAMENTS AUG 1 B1 1 om PRE B-G-1 H2 281 1 QLIG-55 ISIIUTINMP-ES-024504 A-33 IS1 B6 40 2B11 QLIG-55 FLANGE LIGAMENTS AIJG 1 B1 1 om PRE B-G-1 H2 281 1 QLIG-56 ISllUTINMP-ES-024-504 A-33 IS1 B6 40 2B11 QLIG-56 FLANGE LIGAMENTS AIJG 1 Bl I om PRE m o E 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - r 2 5 s----------- - - - - --------- - - - - s----------- - - - - -------- - - - - s----------- - - - - --------- - - - - s----------- - - - - - - - - - - - - s----------- - - - - -------- - - - - s----------- - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - s----------- - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 21 - 27 711 312006 1 Period 1 Period 2 Period 3 N P) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s------- - - - - - - - - - - - - - - - - - - - - - - - - v- 2 5 s----------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----=------- - - - - - - - - - - - - - - - - - - - - - - - - s------- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope I Method I Procedure Code Case B-G-1 H2 281 1PLIG-6 ISllUTINMP-ES-024-504 A-33 IS1 86 40 281 1 QLIG-6 FLANGE LIGAMENTS AUG 1 B1 1 om PRE B-G-1 H2 281 1PLIG-7 ISIIUTI A-33 IS1 86 40 281 1 QLIG-7 FLANGE LIGAMENTS AUG 1 81 1 om PRE B-G-1 H2 281 1\2LIG-8 ISIIUTI A-33 IS1 86.40 281 1 PLIG-8 FLANGE LIGAMENTS AUG 1 81 1 om PRE B-G-1 H2 281 IPLIG-9 ISIIUTI A-33 IS1 86 40 281 1 QLIG-9 FLANGE LIGAMENTS AUG 1 B11 om PRE B-G-1 H2 281 1PWASHER-1 ISllVTINMP-ES-024-201 A-33 IS1 86 50 281 1 QWASHER-1 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE BG-1 H2 281 1PWASHER-10 ISIIVTI A-33 IS1 86 50 281 1 QWASHER-10 CLOSURE HEAD WASHERS AUG 1 81 1 ow pRE B -G-1 H2 281 1PWASHER-11 ISIIVTI A-33 IS1 B6 50 281 1 QWASHER-11 CLOSURE HEAD WASHERS AUG 1 81 1 om pRE B-G-1 H2 281 1PWASHER-12 ISINTI A-33 IS1 86 50 281 1 QWASHER-12 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE B-G-1 H2 281 1 PWASHER-13 ISIIVTI A-33 IS1 86 50 281 1 PWASHER-13 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE B-G-1 H2 281 1QWASHER-14 ISIIVTI A-33 IS1 86 50 281 IPWASHER-14 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE m o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 22 - 27 711 312006 / Period 1 Period 2 Period 3 N rn 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - -s--- - - - - ---- - - - - - - - - - - ---- - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B-G-I H2 281 IDWASHER-15 ISIIVTI A-33 IS1 86.50 281 1 UWASHER-15 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE B-G-I H2 281 112WASHER-16 ISIMI A-33 IS1 86.50 281 1 UWASHER-16 CLOSURE HEAD WASHERS AUG 1 B11 OWN PRE B-G-1 HZ 281 IDWASHER-17 ISIMI A-33 IS1 86.50 281 1 UWASHER-17 CLOSURE HEAD WASHERS AUG 1 B11 OWN PRE B-G-I H2 281 IDWASHER-18 IS IIVTI A-33 IS1 86.50 281 IUWASHER-18 CLOSURE HEAD WASHERS A~G 1 B11 om PRE B-G-I H2 281 1 UWASHER-19 ISIIVTI A-33 IS1 86.50 281 1 WASHER-1 9 CLOSURE HEAD WASHERS AUG 1 B11 om PRE BG-I H2 281 1UWASHER-2 ISIMINMP-ES-024-201 A-33 IS1 86.50 281 1 UWASHER-2 CLOSURE HEAD WASHERS AUG 1 Bl I om PRE B-G-I H2 281 IDWASHER-20 ISIMI A-33 IS1 86.50 281 1UWASHER-20 CLOSURE HEAD WASHERS AUG 1 811 om pRE B-G-I H2 281 IUWASHER-21 ISIIVTI A-33 IS1 86.50 281 1 UWASHER-21 CLOSURE HEAD WASHERS AUG 1 B11 om PRE B-G-I H2 281 1UWASHER-22 I SIIVTI A-33 IS1 B6.50 281 1 UWASHER-22 CLOSURE HEAD WASHERS AUG 1 B11 ow PRE B-G-I H2 281 1UWASHER-23 ISIIVTI A-33 IS1 86.50 281 1UWASHER-23 CLOSURE HEAD WASHERS AUG 1 811 om PRE O) o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 ----s------- - - - - - - - - - - - - S - - - - - - - - - - - - - - - s - - - - - - - - - - - - - - - s - - - - - - - - - - - - - - - ----s------- - - - - - - - - - - - - s----------- - - - - --------- - - - - ----S------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - --------s- - - - - -------- - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 23 - 27 7'1312006 I Period 1 Period 2 Period 3 NC? E 2 5 5 -s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - -s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -S--- - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I CornplD I System Scope I Method I Procedure Code Case B-G-1 H2 281 IDWASHER-24 ISlMl A-33 IS1 86.50 281 1 DWASHER-24 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE B-G-1 H2 281 IDWASHER-25 ISllVTl A-33 IS1 86.50 281 1 DWASHER-25 CLOSURE HEAD WASHERS AUG 1 81 1 OWN PRE B-G-1 H2 281 IDWASHER-26 ISllVTl A-33 IS1 86.50 281 IDWASHER-26 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE B-G-I H2 281 1 DWASHER-27 ISllVTl A-33 IS1 86.50 281 IDWASHER-27 CLOSURE HEAD WASHERS AUG 1 81 I ow PRE B-G-1 H2 281 IDWASHER-28 ISlIVTl A-33 IS1 86.50 281 1 PWASHER-28 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE B-G-1 H2 281 IDWASHER-29 ISllUTl A-33 IS1 86.50 281 1 PWASHER-29 CLOSURE HEAD WASHERS AUG 1 81 I om PRE B-G-I H2 281 IDWASHER-3 ISIMINMP-ES-024-201 A-33 IS1 86.50 281 I DWASHER-3 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE B-G-1 H2 281 IDWASHER-30 lSlMl A-33 IS1 86.50 281 IDWASHER-30 CLOSUREHEADWASHERS AUG 1 81 1 om PRE B-G-1 H2 281 IDWASHER-31 ISliWl A-33 IS1 86.50 281 1 DWASHER-31 CLOSURE HEAD WASHERS AUG 1 81 1 ow PRE B-G-1 H2 281 IDWASHER-32 ISliWl A-33 IS1 86.50 281 1 DWASHER-32 CLOSURE HEAD WASHERS AUG 1 81 1 OWN PRE m o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r E 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - s----------- - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 24 - 27 711 312006 1 Period 1 Period 2 Period 3 (Y m 2 2 5 5 s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - -s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. IternNO, Comp. Desc.

Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B-G-1 H2 281 1 UWASHER-33 ISIIVTI A-33 IS1 B6.50 281 1 QWASHER-33 CLOSURE HEAD WASHERS AUG 1 B11 om PRE B-G-I H2 281 1 UWASHER-34 ISllVTI A-33 IS1 B6 50 281 1 QWASHER-34 CLOSURE HEAD WASHERS AUG 1 B11 om PRE B-G-I H2 2B1 IUWASHER-35 ISIIVTI A-33 IS1 B6 50 281 1 QWASHER-35 CLOSURE HEAD WASHERS AUG 1 Ell om PRE B-G-1 H2 281 IDWASHER-36 ISIIVTI A-33 IS1 B6 50 281 1 UWASHER-36 CLOSURE HEAD WASHERS AUG 1 81 1 om PRE B-G-1 H2 281 IDWASHER-37 ISIIVTI A-33 IS1 B6 50 281 1 QWASHER-37 CLOSURE HEAD WASHERS AUG 1 B11 OWN PRE B-G-I H2 281 IQWASHER-38 ISIIVTI A-33 IS1 B6 50 281 1 QWASHER-38 CLOSURE HEAD WASHERS AUG 1 B11 om PRE B-G-1 H2 281 1 QWASHER-39 ISIIVTI A-33 IS1 B6 50 2B11 QWASHER-39 CLOSURE HEAD WASHERS AUG 1 Bll om PRE B-G-1 H2 281 IUWASHER-4 ISIMINMP-ES-024-201 A-33 IS1 B6 50 281 1 QWASHER-4 CLOSURE HEAD WASHERS AUG 1 B11 om PRE B-G-1 H2 281 1QWASHER-40 lSllVT1 A-33 IS1 86 50 281 1 QWASHER-40 CLOSURE HEAD WASHERS AUG 1 B11 OWN PRE B-G-I H2 281 1QWASHER-41 ISIMINMP-ES-024-201 A-33 IS1 B6 50 281 IDWASHER-41 CLOSURE HEAD WASHERS AUG 1 B11 om PRE $ z P! P! 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s----------- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - s----------- - - - - - - - - - - - -

Revision:

1 HNP-2 Fourth lnterval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope I Method I Procedure Code Case 6-G-1 H2 281 IDWASHER-42 ISIIVTINMP-ES-024201 A-33 IS1 B6 50 281 1UWASHER-42 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE 6-G-1 H2 281 1 DWASHER-43 ISIIVTINMP-ES-024201 A-33 IS1 B6 50 281 IDWASHER-43 CLOSURE HEAD WASHERS AUG 1 81 1 OWN PRE 6-G-1 H2 281 IDWASHER-44 ISINTINMP-ES-024201 A-33 IS1 86 50 281 IDWASHER-44 CLOSURE HEAD WASHERS AUG 1 81 1 OWN PRE 6-G-1 H2 281 1 DWASHER-45 ISIIVTINMP-ES-024201 A-33 IS1 86 50 281 IDWASHER-45 CLOSURE HEAD WASHERS AUG 1 B11 OWN PRE 6-G-1 H2 281 IDWASHER-46 ISIIVTINMP-ES-024201 A-33 IS1 86 50 281 1UWASHER-46 CLOSURE HEAD WASHERS AUG 1 81 1 OWN PRE 6-G-1 H2 281 IDWASHER-47 ISI/VT/NM~~-ES-024201 A-33 IS1 86 50 281 1UWASHER-47 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE 6-G-1 H2 281 IDWASHER-48 ISIIVTINMP-ES-024201 A-33 IS1 86 50 281 IDWASHER-48 CLOSURE HEAD WASHERS AUG 1 81 1 OWN PRE 64-1 H2 281 IDWASHER-49 ISIIVTINMP-ES-024-201 A-33 IS1 86 50 281 1\2WASHER-49 CLOSURE HEAD WASHERS AUG 1 81 1 OWN PRE B -G-1 H2 281 1 DWASHER-5 ISIMINMP-ES-024201 A-33 IS1 86 50 281 1 UWASHER-5 CLOSURE HEAD WASHERS AUG 1 81 1 OWN PRE B-G-1 H2 281 IDWASHER-50 ISllVTINMP-ES-024-201 A-33 IS1 86 50 281 1 UWASHER-50 CLOSURE HEAD WASHERS AUG 1 B11 OWN PRE Page 25 - 27 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary

/ ComplD / System Scope I Method I Procedure Code Case B-G-1 H2 281 IDWASHER-51 ISINTINMP-ES-024-201 A-33 IS1 B6 50 281 1 PWASHER-51 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE B-G-1 H2 281 1PWASHER-52 ISllVTINMP-ES-024-201 A-33 IS1 B6 50 281 1 PWASHER-52 CLOSURE HEAD WASHERS AUG 1 Bl 1 OWN PRE B -G-I H2 281 1PWASHER-53 ISllVTINMP-ES-024-201 A-33 IS1 B6 50 281 1 PWASHER-53 CLOSURE HEAD WASHERS AUG 1 Bl I OWN PRE B-G-1 H2 281 IDWASHER-54 ISllVTINMP-ES-024-201 A-33 IS1 B6 50 281 1 PWASHER-54 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE B-G-1 H2 281 IDWASHER-55 ISINT/NMP-ES-O~~-~O~

A-33 IS1 B6 50 281 1 PWASHER-55 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE B-G-I H2 281 IPWASHER-56 ISINTINMP-ES-024-201 A-33 IS1 B6 50 281 1 PWASHER-56 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE 943-1 H2 281 IDWASHER-6 ISIIVTINMP-ES-024-201 A-33 IS1 86.50 281 1 PWASHER-6 CLOSURE HEAD WASHERS AUG 1 Bll OWN PR E B-G-I H2 281 1PWASHER-7 ISIIVTI A-33 IS1 B6 50 281 1 PWASHER-7 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE B-G-I H2 281 1PWASHER-8 ISIIVTI A-33 IS1 B6 50 281 1 PWASHER-8 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE B-G-I H2 281 IDWASHER-9 ISlMl A-33 IS1 86 50 2B11 DWASHER-9 CLOSURE HEAD WASHERS AUG 1 Bll OWN PRE Page 26 - 27 Period 1 Period 2 Period 3

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Period 1 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B-G-2 H2 2B21\1 CHSV-1 FB A-3 IS1 87.50 2B21\1CHSV-1 FB GR 1 FLANGE BOLTING AUG 1 82 1 OWN PRE B-G-2 H2 2821-1 MS-8A-ASR-2FB A-5 IS1 87.50 2821-1 MS-8A-ASR-2FB 2821-F013B GR 2 FLANGE BOLTING AUG 1 821 OWN PRE B -G -2 H2 2821-1 MS-8A-BSR-2FB A-5 IS1 87.50 2821 -1 MS-8A-BSR-2FB 2821-F013A GR 2 FLANGE BOLTING AUG 1 OWN PRE B -G -2 H2 2821 -1 MS-8B-ASR-2FB A-5 IS1 87.50 2821 -1 MS-8B-ASR-2FB 2821-F013K GR 2 FLANGE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2B21-1 MS-8B-BSR-2FB A-5 IS1 87.50 2821

-1 MS-8B-BSR-2FB 2821 -F013D GR 2 FLANGE BOLTING AUG 1 82 1 OWN PRE B-G-2 H2 2B21-1 MS-8B-CSR-2FB A-5 IS1 87.50 2821

-1 MS-8B-CSR-2FB 2821 -F013C GR 2 FLANGE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821-1MS-8B-DSR-2FB A-5 IS1 87.50 2821-1 MS-88-DSR-2FB 2821-F013E GR 2 FLANGE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821-1 MS-8C-ASR-2FB A-5 IS1 87.50 2821 -1 MS-8C-ASR-2FB 2821-F013L GR 2 FLANGE BOLTING AUG 1 82 1 OWN PRE B -G -2 H2 2821 -1 MS-8C-BSR-2FB A-5 IS1 87.50 2821

-1 MS-8C-BSR-2FB 2821 -F013G GR 2 FLANGE BOLTING AUG 1 821 OWN PRE B -G -2 H2 2821-1 MS-8C-CSR-2FB A-5 IS1 87.50 2B21-1 MS-8C-CSR-2FB 2821-F013F GR 2 FLANGE BOLTING AUG 1 821 OWN PRE Page 1 - 7 Period 2 Period 3 I Revision:

1 Category, ItemNO, HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Period 1 Iso No. Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-2 H2 2821-1 MS-8D-ASR-2FB A-5 IS1 87.50 2821 -1MS-8D-ASR-2FB 2821 -F013J GR 2 FLANGE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821-1 MS-8D-BSR-2FB A-5 IS1 87.50 2821

-1 MS-8D-BSR-2FB 2821-F013H GR 2 FLANGE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2831 -1 RCM-28AS-9BC-4FB A-16 IS1 87 50 2831 -1 RCM-28AS-9BC-4FB 4 GR 3 FLANGE BOLTING AUG 1 831 OWN PRE B-G -2 H2 2831-1 RCM-28BS-8BC-4FB A-18 IS1 87.50 2831 -1 RCM-28BS-8BC-4FB 4" GR 3 FLANGE BOLTING AUG 1 831 OWN PRE B-G-2 H2 2E11-1 RHR-9A-HS-1 FB A-20 IS1 87 50 2E11-1 RHR-9A-HS-1 FB 2N6A GR 4 FLANGE BOLTING AUG 1 El I OWN PRE B-G-2 H2 2E11-1 RHR-9B-HS-1 FB A-20 IS1 87.50 2E11-1 RHR-9B-HS-1 FB 2N6B GR 4 FLANGE BOLTING AUG 1 El 1 OWN PRE B-G-2 H2 2821-F010A BOLTING A-12 IS1 87.70 2821 -F010A BOLTING GROUP 1 VALVE BOLTING AUG 1 821 OWN PRE B -G -2 H2 2821-F01OB BOLTING A-13 IS1 87.70 2821 -FOlOB BOLTING 1 821 GROUP 1 VALVE BOLTING AUG OWN PRE B-G-2 H2 2821-F011A BOLTING A-I 2 IS1 87.70 2821-F011A BOLTING GROUP 2 VALVE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821-F011 B BOLTING A-13 IS1 87.70 2821-F011 B BOLTING GROUP 2 VALVE BOLTING AUG 1 821 OWN PRE Page 2 - 7 Period 2 Period 3 4 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 3 - 7 7/13/2006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method / Procedure Code Case B-G-2 H2 2821-F013A BOLTING A-5 IS1 87.70 2821-F013A BOLTING GROUP 3 VALVE BOLTING AUG 1 82 1 OWN PRE B-G-2 H2 2821-F013B BOLTING A-5 IS1 87.70 2821 -F013B BOLTING GROUP 3 VALVE BOLTING AUG 1 82 1 ow pRE B-G-2 H2 2821-F013C BOLTING A-5 IS1 87.70 2821 -F013C BOLTING GROUP 3 VALVE BOLTING AUG 1 82 1 OWN PRE B-G-2 H2 2B21-F013D BOLTING A-5 IS1 87.70 2821 -F013D BOLTING GROUP 3 VALVE BOLTING AUG 1 82 1 ow PRE B -G -2 H2 2821-F013E BOLTING A-5 IS1 87 70 2821 -F013E BOLTING GROUP 3 VALVE BOLTING AUG 1 82 1 ow PRE B-G-2 H2 2B21-F013F BOLTING A-5 IS1 87.70 2821 -F013F BOLTING GROUP 3 VALVE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821-F013G BOLTING A-5 IS1 87.70 2821 -F013G BOLTING GROUP 3 VALVE BOLTING AUG 1 821 ow PRE B-G-2 H2 2821-F013H BOLTING A-5 IS1 87.70 2821-F013H BOLTING GROUP 3 VALVE BOLTING AUG 1 82 1 ow PRE B-G-2 H2 2821 -F013K BOLTING A-5 IS1 87 70 2821-F013K BOLTING GROUP 3 VALVE BOLTING AIJG 1 82 1 OWN PRE B-G-2 H2 2821-F013L BOLTING A-5 IS1 87 70 2821-F013L BOLTING GROUP 3 VALVE BOLTING AUG 1 82 1 ow PRE N P) 2 2 $5 $5 tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - m o 2 2 5 5 - - - - - - - - - - - - tt-- - - - - - - - - - -- - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt-- - - - - - - - - - - - - It-- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - F 2 5 tt--t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - t--- - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Period i Category, Iso No. IternNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-2 H2 2821-F013M BOLTING A-5 IS1 87 70 2821 -F013M BOLTING GROUP 3 VALVE BOLTING AUG 1 82 1 OWN PRE B-G-2 H2 2B21-F022A BOLTING A-6 IS1 87 70 2821 -F022A BOLTING GROUP 4 VALVE BOLTING AUG 1 82 1 OWN PRE B-G-2 H2 2821 -F022B BOLTING A-7 IS1 87 70 2821 -F022B BOLTING GROUP 4 VALVE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821-F022C BOLTING A-8 IS1 87.70 2821 -F022C BOLTING GROUP 4 VALVE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821-F022D BOLTING A-9 IS1 87 70 2821 -F022D BOLTING GROUP 4 VALVE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821 -F028A BOLTING A-6 IS1 87.70 2821 -F028A BOLTING GROUP 4 VALVE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821 -F028B BOLTING A-7 IS1 87.70 2821 -F028B BOLTING GROUP 4 VALVE BOLTING AUG 1 821 OWN PRE 8-6-2 H2 2821-F028C BOLTING A-8 IS1 87 70 2821 -F028C BOLTING GROUP 4 VALVE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821-F028D BOLTING A-9 IS1 87 70 2B21-F028D BOLTING GROUP 4 VALVE BOLTING AUG 1 821 OWN PRE B-G-2 H2 2821 -F077A BOLTING A-12 IS1 87 70 2821 -F077A BOLTING GROUP 1 VALVE BOLTING AUG 1 821 OWN PRE Page 4 - 7 711 312006 1 Period 2 Period 3 Revision:

1 Category, ItemNO, HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B -G -2 H2 2821-F077B BOLTING A-13 IS1 87.70 2821 -F077B BOLTING 1 821 GROUP 1 VALVE BOLTING AUG OWN PRE B -G -2 H2 2831-F023A BOLTING A-16 IS1 87.70 2831 -F023A BOLTING 1 83 1 GROUP 5 VALVE BOLTING AUG OWN PRE B -G -2 H2 2831-F023B BOLTING A-18 IS1 87.70 2831 -F023B BOLTING GROUP 5 VALVE BOLTING AUG 1 831 OWN PRE B -G -2 H2 2831-F031 A BOLTING A-17 IS1 87.70 2831-F031A BOLTING GROUP 5 VALVE BOLTING AUG 1 831 OWN PRE B-G-2 H2 2831-F031B BOLTING A-19 IS1 87.70 2831 -F031 B BOLTING GROUP 5 VALVE BOLTING AUG 1 831 OWN PRE B-G-2 H2 2E11-F008 BOLTING A-21 IS1 87.70 2E11 -F008 BOLTING GROUP 6 VALVE BOLTING AUG 1 El 1 OWN PRE B-G-2 H2 2E11-F009 BOLTING A-21 IS1 87.70 2E11 -F009 BOLTING GROUP 6 VALVE BOLTING AUG 1 El 1 OWN PRE 6-G-2 H2 2E11 -F015A BOLTING A-22 IS1 87.70 2E11 -F015A BOLTING 1 El 1 GROUP 7 VALVE BOLTING AUG OWN PRE B -G -2 H2 2E11 -F015B BOLTING A-23 IS1 87.70 2E11 -F015B BOLTING GROUP 7 VALVE BOLTING AUG 1 El 1 OWN PRE B-G-2 H2 2E11-F050A BOLTING A-22 IS1 87.70 2E11-F050A BOLTING GROUP 9 VALVE BOLTING AUG 1 El 1 OWN PRE Period 1 a 0 E 2 2 5 Page 5 - 7 Period 2 E I I

• 711312006 1 Period 3 (Y 0 l2 2 IN 5 4 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 6 - 7 711 312006 1 Period 1 Period 2 Period 3 N P) 2 2 5 5 tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-2 HZ 2E11-F050B BOLTING A-23 ISI 87.70 2E11 -F050B BOLTING GROUP 9 VALVE BOLTING AuG 1 El 1 om PRE B -G -2 H2 2E11-F060A BOLTING A-22 IS1 87.70 2E11 -F060A BOLTING GROUP 10 VALVE BOLTING AUG 1 El 1 OWN PRE B-G-2 H2 2E11-F060B BOLTING A-23 IS1 87 70 2E11 -F060B BOLTING GROUP 10 VALVE BOLTING AUG 1 El 1 om PRE B-G-2 H2 2E11-F067 BOLTING A-21 IS1 87.70 2E11 -F067 BOLTING GROUP 8 VALVE BOLTING AUG 1 El 1 om pRE B -G -2 H2 2E21-F004A BOLTING A-24 IS1 87 70 2E21 -F004A BOLTING GROUP 11 VALVE BOLTING AUG 1 E21 om PRE B -G -2 H2 2E21-F004B BOLTING A-25 IS1 87 70 2E21 -F004B BOLTING GROUP 11 VALVE BOLTING AUG 1 E21 om PRE B -G -2 H2 2E21-F005A BOLTING A-24 IS1 87.70 2E21 -F005A BOLTING GROUP 11 VALVE BOLTING AUG 1 E21 om PRE B -G -2 H2 2E21 -F005B BOLTING A-25 IS1 87.70 2E21 -F005B BOLTING GROUP 11 VALVE BOLTING AUG 1 E21 om PRE B -G -2 H2 2E21-F006A BOLTING A-24 IS1 87.70 2E21 -F006A BOLTING GROUP 12 VALVE BOLTING AUG 1 E21 om PRE B -G -2 HZ 2E21-F006B BOLTING A-25 IS1 87 70 2E21 -F006B BOLTING GROUP 12 VALVE BOLTING AUG 1 E21 OWN PRE 0) o 2 2 5 5 tt-- - - - - - - - - - - - - - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt-- - - - - - - - - - - - - r 2 5 t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - t--- - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 7 - 7 711 312006 ( Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case 86-2 H2 2E21 -F007A BOLTING A-24 IS1 87.70 2E21 -F007A BOLTING GROUP 13 VALVE BOLTING AIJG 1 E21 om PRE B -G -2 H2 2E21-F007B BOLTING A-25 IS1 87.70 2E21 -F007B BOLTING GROUP 13 VALVE BOLTING AUG 1 E2 1 om PRE 6-G-2 H2 2E41 -F002 BOLTING A-26 IS1 87.70 2E41 -F002 BOLTING GROUP 15 VALVE BOLTING AIJG 1 E41 om PRE 6 -G -2 H2 2E41-F003 BOLTING A-26 IS1 87.70 2E41 -F003 BOLTING GROUP 15 VALVE BOLTING AUG 1 E41 om PRE B -G -2 H2 2E41 -F006 BOLTING A-26 IS1 87.70 2E41 -F006 BOLTING GROUP 14 VALVE BOLTING AUG 1 E4 1 om PRE B -G -2 H2 2G31 -Fool BOLTING A-28 IS1 87.70 2G31-F001 BOLTING GROUP 16 VALVE BOLTING AUG 1 G31 OWN PRE B -G -2 H2 2G31-F004 BOLTING A-28 IS1 87.70 2G31-F004 BOLTING GROUP 16 VALVE BOLTING AUG 1 G31 om PRE B -G -2 H2 2G31-F027 BOLTING A-28 IS1 87.70 2G31-F027 BOLTING GROUP 17 VALVE BOLTING AUG 1 G31 om PRE CY o 2 2 5 I, tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - m o 2 2 5 5 tt-- - - - - - - - - - - - - tt-- - - - - - - - - - ; - - - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - F 2 5 t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - t--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - t--- - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2821 -1 CHSV-4-1 A-3 IS1 Page 1 - 30 711312006 1 Period 1 Period 2 Period 3 4' DIA. NOZZLE TO FLANGE AUG ---- PRE B J H2 2821-1 FW-12AA-1 A-10 IS1 89.1 1 2821 -1 FW-12AA-1 REDUCER TO PIPE AUG 1 821 OWN PRE - - - - B-J H2 2821 -1 FW-12AA-11 lSllUT1 A-1 0 IS1 -s-- 89.1 1 2821-1 FW-12AA-11 CS TRANS PIECETO CSTRANS PIECE AUG - - - - CS TRANS PIECE TO NOZZLE AUG ---- PRE - - - - - - - - B-J H2 2821-1 FW-12AA-2 A-10 IS1 - - - - - - - - PlPE TO PlPE AUG ---- PRE - - - - B J H2 2821-1 FW-12AA-3 A-10 IS1 ---- 89.11 2821

-1 FW-12AA-3 PIPE TO PIPE AUG - - - - 1 821 OWN - - - - PRE B J H2 2821-1 FW-12AA-4 A-1 0 IS1 89.1 1 2821 -1 FW-12AA-4 PIPE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 FW-12AA-5 A-1 0 ISI 89.1 1 2821 -1 FW-l2AA-5 PIPE TO ELBOW AUG 1 82 1 OWN PRE B J H2 2821-1 FW-12AA-6 A-1 0 IS1 89.1 1 2821 -1 FW-12AA-6 ELBOW TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 FW-12AA-7 lSllUT1 A-1 0 IS1 89.1 1 2821 -1 FW-12AA-7 PIPE TO TRANSITION PIECE AUG 1 821 OWN PRE 4 Revision:

1 HNP-2 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company Page 2 - 30 711 312006 1 Period 1 Period 2 Period 3 N (3 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2821-1 FW-12AB-1 A-1 0 IS1 89.11 2821-1 FW-12AB-1 REDUCER TO PIPE AUG 1 821 om PRE B-J H2 2821-1 FW-12AB-10 A-1 0 IS1 89.1 1 2821 -1 FW-12AB-10 PIPE TO TRANSITION PIECE AUG 1 821 om PRE B J H2 2821 -1 FW-12AB-14 ISIIUTI A-1 0 IS1 89.1 1 2821 -1 FW-12AB-14 PIECE AUG 1 821 om PRE B J H2 2821-1 FW-12AB-15 ISI/UTl A-1 0 IS1 89.1 1 2821 -1 FW-1x8-15 TRANSITION PIECE TO NOZZLE AUG 1 821 om PRE B-J H2 2821 -1 FW-1 2AB-1A A-1 0 IS1 89.1 1 2821 -1 FW-12AB-1 A PIPE TO ELBOW AUG 1 821 om PRE B J H2 2821-1 FW-12AB-2 A-1 0 IS1 89.1 1 2821 -1 FW-12AB-2 ELBOW TO PIPE AUG 1 82 1 om PRE B-J H2 2821 -1 FW-12AB-3 A-1 0 IS1 89.1 1 2821 -1 FW-12AB-3 PIPE TO ELBOW AUG 1 82 1 om PRE B J H2 2821 -1 FW-12AB-4 A-1 0 IS1 89.1 1 2821 -1 FW-1x8-4 ELBOW TO PIPE AUG 1 821 om PRE B J H2 2821-1 FW-12AB-5 A-1 0 IS1 89.1 1 2821 -1 FW-12AB-5 PIPE TO ELBOW AUG 1 821 om PRE B J HZ 2821 -1 FW-12AB-6 A-1 O IS1 89.1 1 2821 -1 FW-12AB-6 ELBOWTO PIPE AUG 1 821 om PRE m o z 2 5 - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s--s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 3 - 30 711 312006 1 Period 1 Period 2 Period 3 N o 2 2 5 i4 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - ------------ - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - . - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope I Method I I Procedure Code Case B J H2 2821-1 FW-12AB-7 A-1 0 IS1 B9 11 2B21-1 FW-12AB-7 PIPE TO PIPE AUG 1 821 om PRE B J H2 2821-1 FW-12AB-8 A-1 0 IS1 89 11 2B21-1 FW-12AB-8 PIPE TO ELBOW AUG 1 821 om I PRE B J H2 2821-1 FW-12AB-9 ISIIUTI A-1 0 IS1 B9 11 2821 -1 FW-12AB-9 ELBOWTO PIPE AUG 1 82 1 om PRE B J H2 2821-1 FW-12BC-1 A-1 1 IS1 89 11 2B21-1 FW-12BC-1 REDUCER TO ELBOW AUG 1 821 om PRE B-J H2 2821-1 FW-12BC-10 ISllUTl A-1 1 IS1 89 11 2B21-1 FW-12BC-10 PIPE TO TRANSITION PIECE AUG 1 821 I om PRE B J H2 2821 -1 FW-12BC-14 A-1 1 IS1 B9 11 2B21-1 FW-12BC-14 PIECE AUG 1 821 om PRE B J H2 2821-1 FW-12BC-15 lSllUT1 A-1 1 IS1 89 11 2821 -1 FW-12BC-15 TRANSITION PIECE TO NOZZLE AUG 1 821 om PRE BJ H2 2821 -1 FW-12BC-1 A A-1 1 IS1 89 11 2821 -1 FW-12BC-1 A PIPE TO ELBOW AUG 1 821 om PRE B J H2 2821 -1 FW-12BC-2 A-1 1 IS1 89 11 2821 -1 FW-12BC-2 ELBOW TO PIPE AUG 1 821 om PRE B J H2 2821 -1 FW-12BC-3 A-1 1 IS1 89 11 2B21-1 FW-12BC-3 PIPE TO ELBOW AUG 1 821 om PRE 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company Period 1 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method 1 Procedure Code Case B J H2 2821 -1 FW-12BC-4 ISllUTl A-I 1 IS1 B9 11 2821 -1 FW-12BC-4 ELBOWTO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 FW-12BC-5 A-1 I IS1 89 11 2821 -1 FW-12BC-5 PIPE TO ELBOW AUG 1 82 1 OWN PRE B J H2 2821-1 FW-12BC-6 A-I 1 IS1 89 11 2821 -1 FW-12BC-6 ELBOW TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 FW-128C-7 A-1 1 IS1 89 11 2821 -1 FW-12BC-7 PIPE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 FW-12BC-8 A-1 1 IS1 89 11 2821 -1 FW-12BC-8 PIPE TO ELBOW AUG 1 821 OWN PRE B J H2 2821-1 FW-12BC-9 A-1 I IS1 B9 11 2821-1 FW-12BC-9 ELBOW TO PIPE AUG 1 821 OWN PRE B J H2 2821-1 FW-128D-1 A-1 1 IS1 89 11 2821 -1 FW-12BD-1 REDUCER TO PIPE AUG 1 82 1 OWN PRE B J H2 2821-1 FW-1280-11 ISllUTl A-l I IS\ 89 11 2821 -1 FW-12BD-I1 PIECE AUG 1 821 OWN I I PRE 6 J H2 2821-1 FW-12BD-12 ISIIUTI A-1 I IS1 89 11 2821 -1 FW-12BD-12 TRANSITION PIECE TO NOZZLE AUG 1 821 OWN PRE B J H2 2821-1 FW-128D-1A A-1 1 IS1 89 11 2821 -1 FW-12BD-1 A PIPE TO PIPE AUG 1 82 1 OWN PRE 'age 4 - 30 Period 2 Y 2 5 Period 3 Revision:

1 Category, IternNO, HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary 1 CornplD I System Scope 1 Mdthod 1 Procedure Code Case B J H2 2821 -1 FW-12BD-2 A-1 1 IS1 PlPE TO PlPE AUG OWN PRE B-J H2 2821 -1 FW-12BD-3 A-1 1 IS1 89.1 1 2821-1 FW-12BD-3 PIPE TO PIPE AUG 1 821 OWN PRE B-J H2 2821 -1 FW-12BD-4 A-1 1 IS1 89.1 1 2821-1 FW-12BD-4 PIPE TO PIPE AUG 1 82 1 OWN PRE B-J H2 2821 -1 FW-12BD-5 A-1 1 IS1 89.1 1 2821-1 FW-12BD-5 PIPE TO ELBOW AUG 1 821 OWN PRE B-J H2 2821 -1 FW-12BD-6 A-1 1 IS1 89.1 1 2821-1 FW-12BD-6 ELBOW TO PIPE AUG 1 82 1 OWN PRE B J H2 2821 -1 FW-12BD-7 A-1 1 IS1 PIPE TO TRANSITION PIECE AUG OWN PRE B-J H2 2821 -1 FW-18A-1 lSllUT1 A-12 IS1 89.1 1 2821 -1 FW-18A-1 AUGIUTI VALVE TO PIPE AUG 1 82 1 OWN PRE B J H2 2821 -1 FW-18A-I A ISIIUTI A-I 2 IS1 89.1 1 2821-1 FW-18A-1 A AUGIUTI PIPE TO PENETRATION AUG 1 821 OWN PRE B-J H2 2821-1 FW-18A-2 AUGIUTINMP-ES-024-502 A-12 IS1 89.1 1 2821-1 FW-18A-2 PENETRATION TO VALVE AUG 1 821 OWN PRE B-J H2 2821 -1 FW-18A-3 A-12 IS1 VALVE TO PlPE AUG OWN PRE Page 5 - 30 711 312006 1 Period 1 Period 2 Period 3 d Revision:

1 Category, IternNO, 3 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc.

Class Summary I CornplD I System Scope I Method I Procedure Code Case B J H2 2821-1 FW-18A-4 A-12 IS1 89.1 1 2821 -1 FW-18A-4 PIPE TO ELBOW AUG 1 821 OWN PRE B J H2 2821 -1 FW-18A-5 A-12 IS1 89.1 1 2821 -1 FW-18A-5 ELBOW TO VALVE AUG 1 821 OWN PRE B J H2 2821-1 FW-18A-6 A-12 IS1 89.1 1 2821 -1 FW-18A-6 VALVE TO PIPE AUG 1 82 1 OWN PRE B J H2 2821-1 FW-18A-7 A-12 IS1 89.1 1 2821-1 FW-18A-7 PIPE TO TEE AUG 1 821 OWN PRE B J H2 2821 -1 FW-18A-8 A-12 IS1 89.1 1 2821 -1 FW-18A-8 TEE TO REDUCER AUG 1 82 1 OWN PRE B J H2 2821 -1 FW-18A-9 A-12 IS1 89.1 1 2821 -1 FW-18A-9 TEE TO REDUCER AU G 1 821 OWN PRE B J H2 2821-1 FW-188-1 AUGIUTINMP-ES-024-502 A-13 IS1 89.1 1 2821 -1 FW-188-1 VALVE TO PIPE AUG 1 82 1 OWN PRE B J H2 2821 -1 FW-188-1A ISIIUTI A-13 IS1 89.11 2821 -1 FW-1 88-1 A AUGlUTl PIPE TO PENETRATION AUG 1 821 OWN PRE B-J H2 2821-1 FW-188-2A lSllUT1 A-13 IS1 89.1 1 2821 -1 FW-188-2A AUGII PENETRATION TO VALVE AUG 1 82 1 OWN PRE B-J H2 2821-1 FW-188-3A A-13 IS1 89.1 1 2821 -1 FW-1 88-3A VALVE TO PIPE AUG 1 821 OWN PRE Page 6 - 30 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 7 - 30 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B J H2 2821-1 FW-188-4 A-1 3 IS1 PlPE TO ELBOW AUG OWN PRE B J H2 2821 -1 FW-188-5 A-1 3 IS1 89.1 1 2821 -1 FW-188-5 ELBOW TO VALVE AUG 1 821 OWN PRE B J H2 2821-1 FW-188-6 A-1 3 IS1 89.1 1 2821 -1 FW-188-6 VALVE TO PIPE AUG 1 821 OWN PRE B-J H2 2821-1 FW-188-7 A-1 3 IS1 89.1 1 2821 -1 FW-188-7 PIPE TO TEE AUG 1 821 OWN PRE B J H2 2821-1 FW-188-8 A-1 3 IS1 89.1 1 2021-1 FW-188-8 TEE TO REDUCER AUG 1 821 OWN PRE B J H2 2821-1 FW-188-9 A-1 3 IS1 89.1 1 2021 -1 FW-188-9 TEE TO REDUCER AUG 1 821 OWN PRE B J H2 2821-1 MS-24A-1 ISIII A-6 IS1 89.1 1 2021 -1 MS-24A-1 NOZZLE TO TRANSITION PIECE AUG 1 821 OWN PRE BJ H2 2821 -1 MS-24A-10 A-6 IS1 89.1 1 2821 -1 MS-24A-10 PIPE TO ELBOW AUG 1 821 OWN PRE B J H2 2821-1 MS-24A-11 A-6 IS1 89.1 1 2821 -1 MS-24A-11 ELBOW TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24A-12 A-6 IS1 PlPE TO PlPE AUG OWN PRE Period 1 Period 2 Period 3 4 Revision:

1 3 HNP-2 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company 3 Page 8 - 30 711 312006 1 Period 1 Period 2 Period 3 (Y C) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-J H2 2821 -1 MS-24A-13 A-6 IS1 89 11 2821 -lMS-24A-13 PIPE TO ELBOW AUG 1 821 OWN PRE 6-J H2 2821 -1 MS-24A-14 A-6 IS1 89 11 2821 -1 MS-24A-14 ELBOW TO PIPE AUG 1 821 om PRE B-J H2 2821 -1 MS-24A-15 A-6 IS1 89 11 2821 -1 MS-24A-15 PIPE TO 45-DEGREE ELBOW AUG 1 821 om PRE 6 J H2 2821 -1 MS-24A-16 A-6 IS1 89 11 2821 -1 MS-24A-16 45-DEGREE ELBOW TO PIPE AUG 1 821 om PRE 6-J H2 2821-1 MS-24A-17 A-6 IS1 89 11 2821-1 MS-24A-17 PIPE TO VALVE AUG 1 821 OWN PRE 6 J H2 2821-1 MS-24A-18 ISIIUTI A-6 IS1 89 11 2821 -1 MS-24A-18 AUGIUTI VALVE TO PIPE AUG 1 821 OWN PRE 6-J H2 2821-1 MS-24A-19 ISllUTINMP-ES-024-502 A-6 IS1 89 11 2821 -1 MS-24A-19 AUGIUTINMP-ES-024-502 PIPE TO PIPE AUG 1 82 1 OWN PRE B J H2 2821 -1 MS-24A-2 ISIIUTI A-6 IS1 89 11 2821 -1 MS-24A-2 TRANSITION PIECE TO PIPE AUG 1 821 om PRE 6-J H2 2821 -1 MS-24A-20 ISIIUTI A-6 IS1 89 11 2821 -1 MS-24A-20 AUGlUTl PIPE TO VALVE AUG 1 821 om PRE B-J H2 2821-1 MS-24A-3 ISIIUTI A-6 IS1 89 11 2821 -1 MS-24A-3 PIPE TO ELBOW AUG 1 82 1 OWN PRE O) o 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - r $ 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------*--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - s----------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - S - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. IternNO, Cornp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2821 -1 MS-24A-4 A-6 IS1 89 11 2821 -1 MS-24A-4 ELBOW TO PIPE AUG 1 821 OWN PRE B J H2 2821-1 MS-24A-5 A-6 IS1 89 11 2821 -1 MS-24A-5 PIPE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24A-6 A-6 IS1 89 11 2821 -1 MS-24A-6 PIPE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24A-7 A-6 IS1 89 11 2821 -1 MS-24A-7 PIPE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24A-8 ISIIUTI A-6 IS1 89.1 1 2821 -1 MS-24A-8 PIPE TO ELBOW AUG 1 821 OWN PRE B J H2 2821 -1 MS-24A-9 A-6 IS1 89.1 1 2821 -1 MS-24A-9 ELBOW TO PIPE AUG 1 821 OWN PRE B-J ASR A-6 IS1 89.31 2821 -1 MS-24A-9BC-112821-1 MS-8A-ASR PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE BJ BSR A-6 IS1 89.31 2821 -1 MS-24A-9BC-212821-1 MS-8A-BSR PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B J D ISIIUTINMP-ES-024-502 A-6 IS1 89.31 2821 -1 MS-24A-9BC-312E51-1 RCIC-CD PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B J H2 2821 -1 MS-248-1 ISIIUTI A-7 IS1 89.1 1 2821 -1 MS-240-1 NOZZLE TO TRANSITION PIECE AUG 1 821 OWN PRE Page 9 - 30 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 10 - 30 711 312006 1 Period 1 Period 2 Period 3 N P) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - --- - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B J H2 2821 -1 MS-24B-10 ISIIUTI A-7 IS1 89.1 1 2821 -1 MS-24B-10 PIPE TO ELBOW AUG 1 821 om PRE B J H2 2821-1 MS-24B-11 A-7 IS1 89.1 1 2821 -1 MS-24B-11 ELBOW TO PIPE AUG 1 821 om PRE B J H2 2B21-1 MS-24B-12 A -7 1SI 89.1 1 2821 -1 MS-24B-12 PIPE TO PIPE AUG 1 821 om PRE B J H2 2821 -1 MS-24B-13 A-7 IS1 89.1 1 2821 -1 MS-24B-13 PIPE TO ELBOW AUG 1 821 om PRE B J H2 2821 -1 MS-248-14 A-7 IS1 89.1 1 2821 -1 MS-24B-14 ELBOW TO PIPE AUG 1 821 om PRE B J H2 2821-1 MS-248-15 A-7 IS1 89.1 1 2821 -lMS-24B-15 PIPE TO VALVE AUG 1 821 om PRE B J H2 2821-1 MS-24B-16 AUGIUTINMP-ES-024-502 A-7 IS1 89.11 2821 -1 MS-246-16 VALVE TO PIPE AUG 1 821 om PRE B J H2 2821 -1 MS-248-17 AUGIUTINMP-ES-024-502 A-7 IS1 89.1 1 2821 -1 MS-248-17 PIPE TO PIPE AuG 1 B21 om PRE B J H2 2821-1 MS-24B-18 AUGIUTINMP-ES-024-502 A-7 IS1 89.1 1 2821-1MS-24B-18 PIPE TO VALVE AUG 1 821 om PRE B J H2 2821 -1 MS-24B-2 ISIIUTI A-7 IS1 89.1 1 2821 -1 MS-248-2 TRANSITION PIECE TO PIPE AUG 1 821 om PRE OY o 5 2 5 5 - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s - - - - - - - - - - - s - - - - - - - s - - - - - - - - - - - - - - - - - - - .- 2 5 --------s--- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - --------- - - - - ------------ - - - - - - - - - - - - -..---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - --------- - - - - ------------ - - - - --------- - - - - ----s------- - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company 3 Page 12 - 30 711 312006 1 Period 1 Period 2 Period 3 I? 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - Category, lso No. ItemNO, ~omp. Desc. Class Summary I ComplD 1 System Scope I Method I Procedure Code Case 6 J H2 2821 -1 MS-248-9 A-7 IS1 89.1 1 2821 -1 MS-248-9 PIPE TO PIPE AUG 1 821 om PRE 6 J H2 2821-1 MS-24C-1 ISllUTlNMP-ES-024-502 A-8 IS1 89.1 1 2821 -1 MS-24C-1 NOZZLE TO TRANSITION PIECE AUG 1 82 1 om PRE B J H2 2821 -1 MS-24C-10 A-8 IS1 89.1 1 2821 -1 MS-24C-10 PIPE TO ELBOW AUG 1 821 OWN PRE 6 J H2 2821 -1 MS-24C-11 A-8 IS1 89.1 1 2821 -1 MS-24C-11 ELBOW TO PIPE AUG 1 82 1 om PRE 6 J H2 2821 -1 MS-24C-12 A-8 IS1 89.1 1 2821 -1 MS-24C-12 PIPE TO PIPE AUG 821 1 om PRE 6 J H2 2821-1 MS-24C-13 ISllUTl A-8 IS1 89.1 1 2821 -1 MS-24C-13 PIPE TO ELBOW AUG 1 821 om PRE B J H2 2821 -1 MS-24C-14 A-8 IS1 89.1 1 2821 -1 MS-24C-14 ELBOW TO PIPE AUG 1 82 1 om PRE 6 J H2 2821 -1 MS-24C-15 A-8 IS1 89.1 1 2821

-1 MS-24C-15 PIPE TO VALVE AUG 1 821 om pRE 6 J H2 2821 -1 MS-24C-16 lSllUT1 A-8 IS1 89.1 1 2821

-1 MS-24C-16 AUGIUTI VALVE TO PIPE AUG 1 821 om PRE 6 J H2 2821-1 MS-24C-17 AUGIUTINMP-ES-024-502 A-8 IS1 89.1 1 2821-1 MS-24C-17 PIPE TO PIPE AUG 1 821 OWN PRE m o Z 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s - - - - - - - - - - - r 2 5 ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------s--- - - - - - - - - - - - ------------ - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2821 -1 MS-24C-18 AUGIUTINMP-ES-024-502 A-8 IS1 89 11 2821 -1 MS-24C-18 PIPE TO VALVE AUG 1 82 1 OWN PRE B J H2 2821-1 MS-24C-2 ISIIUTINMP-ES-024502 A-8 IS1 89 11 2821 -1 MS-24C-2 TRANSITION PIECE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24C-3 ISIIUTINMP-ES-024-502 A8 IS1 89 11 2821-1 MS-24C-3 PIPE TO ELBOW AUG 1 821 OWN PRE B-J H2 2821-1 MS-24C-4 A-8 IS1 89 11 2821 -1 MS-24C-4 ELBOW TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24C-5 A-8 IS1 8911 2821 -1 MS-24C-5 PIPE TO PIPE AUG 1 821 OWN PRE B J H2 2821-1 MS-24C-6 A-8 IS1 8911 2821-1 MS-24C-6 PIPE TO PIPE AUG 1 821 OWN PRE B J D A-8 IS1 B9 31 2821 -1 MS-24C-6BC-112E41-1 HPCI-10-D PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B J H2 2821 -1 MS-24C-7 A-8 IS1 89 11 2821-1 MS-24C-7 PIPE TO ELBOW AUG 1 821 OWN PRE B J H2 2821 -1 MS-24C-8 A-8 IS1 89 11 2821 -1 MS-24C-8 ELBOW TO PIPE AUG 1 821 OWN PRE - B J ASR A-8 IS1 89 31 2821 -1MS-24C-8BC-112821-1 MS-8C-ASR PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE Page 13 - 30 Period 1 Period 2 Period 3 V Revision:

1 w HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company u Page 14 - 30 711 312006 / Period 1 Period 2 Period 3 N VJ 2 2 I, 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope I Method I Procedure Code Case B J BSR A-8 IS1 89 31 2821 -1 MS-24C-8BC-212821- 1 MS-8C-BSR PIPE TO BRANCH CONNECTION AUG 1 821 om PRE B J CSR A-8 IS1 89 31 2821 -1 MS-24C-8BC-312821- 1 MS-8C-CSR PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B-J H2 2821-1 MS-24C-9 A-8 IS1 89 11 2821 -1 MS-24C-9 PIPE TO PIPE AUG 1 821 om PRE B J H2 2821 -1 MS-24D-1 ISIIUTINMP-ES-024-502 A-9 IS1 89.1 1 2821 -1 MS-24D-1 NOZZLE TO TRANSITION PIECE AUG 1 821 om PRE B-J H2 2821 -1 MS-24D-10 A-9 IS1 89.1 1 2821 -1 MS-24D-10 PIPE TO ELBOW AUG 1 82 1 OWN PRE B J H2 2821-1 MS-24D-11 A-9 IS1 89.1 1 2B21-1 MS-24D-11 ELBOW TO PIPE AUG 1 821 om PRE B-J H2 2821 -1 MS-24D-12 A-9 IS1 89.1 1 2821 -1 MS-24D-12 PIPE TO PIPE AUG 1 821 om PRE B-J H2 2821 -1 MS-240-13 A-9 IS1 89.1 1 2821 -1 MS-24D-13 PIPE TO ELBOW AUG 1 821 om PRE B-J H2 2821-1 MS-24D-14 A-9 IS1 89.1 1 2821 -lMS-24D-14 ELBOW TO PIPE AUG 1 821 om PRE B-J H2 2821 -1 MS-24D-15 A-9 IS1 89 11 2821-1 MS-24D-15 PIPE TO 45-DEGREE ELBOW AUG 1 821 OWN PRE O) o 2 2 I, I, - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 I, ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - S----------- - - - - - - - - - - - - ..----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----------- - - - - - - - - - - - - -----..------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----------- - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope 1 Method I Procedure Code Case B J H2 2821 -1 MS-24D-16 A-9 IS1 89.1 1 2821-1 MS-24D-16 45-DEGREE ELBOW TO PIPE AUG 1 821 OWN PRE B J H2 2821-1 MS-24D-17 A-9 IS1 89.1 1 2821 -1 MS-24D-17 PIPE TO VALVE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24D-18 AUGIUTINMP-ES-024-502 A-9 IS1 89.1 1 2821

-1 MS-24D-18 VALVE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24D-19 ISllUTlNMP-ES-024502 A-9 IS1 89.1 1 2821 -1 MS-24D-19 AUGIUTINMP-ES-024-502 PIPE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24D-2 ISllUTlNMP-ES-024502 A-9 IS1 89.1 1 2821 -1 MS-24D-2 TRANSITION PIECE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24D-20 AUGIUTINMP-E S-024-502 A-9 IS1 89.1 1 2821 -1 MS-24D-20 PIPE TO VALVE AUG 1 821 OWN PRE 6 J H2 2821 -1 MS-24D-3 ISllUTINMP-ES-024502 A-9 IS1 89.1 1 2821 -1 MS-24D-3 PIPE TO ELBOW AUG 1 821 OWN PRE B J H2 2821-1 MS-24D-4 A-9 IS1 89.1 1 2821 -1 MS-24D-4 ELBOW TO PIPE AUG 1 821 OWN PRE 6 J H2 2821-1 MS-24D-5 A-9 IS1 89.1 1 2821 -lMS-24D-5 PIPE TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-24D-6 A-9 IS1 89.1 1 2821 -1 MS-24D-6 PIPE TO PIPE AUG 1 82 1 OWN PRE Page 15 - 30 Period 1 Period 2 Period 3 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Page 16 - 30 Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2821 -1 MS-24D-7 A-9 IS1 89.1 1 2821 -1 MS-24D-7 PIPE TO PIPE AUG 1 821 OWN PRE B-J H2 2821-1 MS-24D-8 ISIII A-9 IS1 89.1 1 2821 -1 MS-240-8 PIPE TO ELBOW AUG 1 82 1 OWN PRE B J H2 2821 -1 MS-24D-9 ISllUTl A-9 IS1 89.11 2821 -1 MS-24D-9 ELBOW TO PIPE AUG 1 82 1 OWN PRE B J AS R A-9 IS1 89.31 2821 -1MS-24D-9BC-112821-1 MS-8D-ASR PIPE TO BRANCH CONNECTION AUG 1 82 1 OWN PRE B J BSR A-9 IS1 89.31 2821 -1 MS-24D-9BC-212821-1 MS-8D-BSR PIPE TO BRANCH CONNECTION AUG 1 82 1 OWN PRE B J H2 2821-1 MS-8A-ASR-1 ISIII A-5 IS1 89.1 1 2821 -1 MS-8A-ASR-1 BRANCH CONNECTION TO PIPE AUG 1 821 OWN PRE B-J H2 2821 -1 MS-8A-ASR-2 IS111 A-5 IS1 89.1 1 2821 -1 MS-8A-ASR-2 PIPE TO FLANGE AUG 1 821 OWN PRE B J H2 2821 -1 MS-8A-BSR-1 A-5 IS1 89.1 1 2821 -1 MS-BA-BSR-1 BRANCH CONNECTION TO PIPE AUG 1 821 OWN PRE B J H2 2821 -1 MS-8A-BSR-2 A-5 IS1 89.1 1 2821 -1 MS-8A-BSR-2 PIPE TO FLANGE AUG 1 821 OWN PRE B-J H2 2821-1 MS-88-ASR-1 ISIIUTI A-5 IS1 69.11 2821 -1 MS-80-ASR-1 BRANCH CONNECTlON TO PIPE AUG 1 821 OWN PRE Period 1 m o 2 2 Fi Fi ------ - - - - - - - - - - - - - - - - - - - - - - - - - -- - - ---- - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - ---- - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - I - - - - Period 2 F 2 5 -- - - - - - - - - - - - - s - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - -.------ -------- - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - I - - - -

89.1 1 2821 -1 MS-8B-ASR-2 PIPE TO FLANGE AUG 1 821 OWN PRE BJ H2 2821-1 MS-88-BSR-1 ISllUTINMP-ES-024-502 A-5 IS1 89.1 1 2821 -1 MS-8B-BSR-1 BRANCH CONNECTION TO PIPE AUG 1 82 1 OWN PRE B J H2 2B21-1 MS-88-BSR-2 A-5 IS1 89.11 2821 -1 MS-8B-BSR-2 PIPE TO FLANGE AUG 1 82 1 OWN PRE B-J H2 2821-1 MS-8B-CSR-1 A-5 IS1 89.1 1 2821 -1 MS-8B-CSR-1 BRANCH CONNECTION TO PIPE AUG 1 821 OWN PRE B J H2 2821-1 MS-8B-CSR-2 A-5 IS1 89.1 1 2821 -1 MS-8B-CSR-2 PIPE TO FLANGE AUG 1 821 OWN Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Page 17 - 30 711 312006 1 Southern Nuclear Operating Company Period 1 Period 2 Period 3 PRE B J H2 2821-1 MS-8B-DSR-1 A-5 IS1 89.1 1 2821

-1 MS-8B-DSR-1 BRANCH CONNECTION TO PIPE AUG 1 821 OWN PRE B-J H2 2821 -1 MS-88-DSR-2 A-5 IS1 89.1 1 2821 -1 MS-8B-DSR-2 PIPE TO FLANGE AUG 1 821 OWN PRE B J H2 2821 -1 MS-8C-ASR-1 ISllUTINMP-ES-024-502 A-5 IS1 89.1 1 2821 -1 MS-8C-ASR-1 BRANCH CONNECTION TO PIPE AUG 1 B21 OWN PRE B J H2 2821-1 MS-8C-ASR-2 A-5 IS1 N- 2 2 z 5 r 2 i5 ------------

Category, Iso No. IternNO, Comp. Desc. Class Summary 1 CornplD 1 System Scope 1 Method 1 Procedure Code Case B J H2 2821-1 MS-8B-ASR-2 A-5 IS1 Q) o 2 2 5 5 89.1 1 2B21-1 MS-8C-ASR-2 PIPE TO FLANGE AUG 1 82 1 OWN PRE B J H2 2821 -1 MS-8C-BSR-1 ISIIUTI A-5 IS1 89.11 2821 -1 MS-8C-BSR-1 BRANCH CONNECTION TO PIPE AUG 1 82 1 OWN PRE - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

A Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 8 - 30 7H 3R006 ( Period 1 Period 2 Period 3 CY o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .- 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -..---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - - Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope 1 Method 1 Procedure Code Case B J H2 2821 -1 MS-8C-BSR-2 A-5 IS1 89 11 2821 -1 MS-8C-BSR-2 PIPE TO FLANGE AUG 1 821 om pRE B J H2 2821 -1 MS-8C-CSR-1 A-5 ISI 89 11 2821 -1 MS-8C-CSR-1 BRANCH CONNECTION TO PIPE AUG 1 B2 1 om PRE B J H2 2821 -1 MS-8C-CSR-2 A-5 IS1 89 11 2B21-1 MS-8C-CSR-2 PIPE TO FLANGE AUG 1 621 OWN PRE B J H2 2821 -1 MS-8D-ASR-1 A-5 IS1 89 11 2821 -1 MS-8D-ASR-1 BRANCH CONNECTION TO PIPE AUG 1 821 om PRE B-J H2 2821-1 MS-8D-ASR-2 A-5 IS1 89 11 2821 -1 MS-8D-ASR-2 PIPE TO FLANGE AUG 1 821 om PRE B J H2 2821 -1 MS-8D-BSR-1 A-5 ISI 89 11 2821-1 MS-8D-BSR-1 BRANCH CONNECTION TO PIPE AUG 1 82 1 om PRE B-J H2 2821-1 MS-8D-BSR-2 A-5 IS1 89 11 2821 -1 MS-8D-BSR-2 PIPE TO FLANGE AUG 1 821 om pRE B J H2 2E11-1 RHR-20-RS-10 A-2 1 IS1 89 11 2E11-1 RHR-20-RS-10 VALVE TO ELBOW AUG 1 El 1 om PRE B J H2 2E11-1 RHR-20-RS-11 A-21 IS1 89 11 2E11-1 RHR-20-RS-11 ELBOW TO PIPE AUG 1 El 1 om PRE B J H2 2E11-1 RHR-20-RS-11 A ISllUTINMP-ES-024-502 A-21 IS\ 89 11 2E11-1 RHR-20-RS-11A PENETRATION TO PIPE AUG 1 El 1 om PRE m o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 19 - 30 7H 312006 1 Period 1 Period 2 Period 3 N P) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s------- - - - - - - - - - - - - Category, Iso No. IternNO, Comp. Desc. Class Summary I ComplD 1 System Scope I Method I Procedure Code Case 6 J H2 2E11-1 RHR-20-RS-12 A-21 IS1 89.1 1 2E11-1 RHR-20-RS-12 PIPE TO VALVE AUG 1 El 1 OWN PRE 6 J H2 2E11-1 RHR-20-RS-4 ISIIUTINMP-ES-024502 A-21 IS1 89.1 1 2E11-1 RHR-20-RS-4 PIPE TO VALVE AUG 1 El 1 OWN PRE 6 J H2 2E11-1 RHR-20-RS-5 ISIIUTI A-21 IS1 89.1 1 2E11-1 RHR-20-RS-5 VALVE TO ELBOW AUG 1 El 1 OWN PRE 6-J H2 2E11-1 RHR-20-RS-6 A-21 IS1 89.11 2E11-1 RHR-20-RS-6 ELBOW TO PIPE AUG 1 El 1 om PRE 6 J H2 2E11-1 RHR-20-RS-7 A-21 IS1 89.1 1 2E11-1 RHR-20-RS-7 PIPE TO ELBOW AUG 1 El 1 om PRE 6 J H2 2E11-1 RHR-20-RS-8 A-21 IS1 89.1 1 2E11-1 RHR-20-RS-8 ELBOW TO PIPE AUG 1 El 1 om PRE B J H2 2E11-1 RHR-20-RS-9 A-21 IS1 89.1 1 2E11-1 RHR-20-RS-9 PIPE TO VALVE AUG 1 El 1 om PRE B J H2 2E11-1 RHR-24A-R-1 A-22 IS1 89.1 1 2E11-1 RHR-24A-R-1 VALVE TO VALVE AUG 1 El 1 om PRE 6 J H2 2E11-1 RHR-24A-R-1A A-22 IS1 89.11 2E11-1 RHR-24A-R-1A VALVE TO PENETRATION AUG 1 El 1 om PRE 6-J H2 2E11-1 RHR-24A-R-2 ISlll A-22 IS1 89.11 2E11-1 RHR-24A-R-2 PIPE TO ELBOW AUG 1 El 1 OWN PRE Q, o 2 2 55 . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - r 2 5 ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----------- - - - - - - - - - - - - - - - - - - - - - - - -

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Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 21 - 30 711312006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope I Mithod 1 Procedure Code Case B J H2 2E11-1 RHR-24B-R-1A A-23 IS1 89.1 1 2Ell-1 RHR-240-R-1 A VALVE TO PENETRATION AUG 1 El 1 om I PRE B J H2 2E11-1 RHR-24B-R-2 ISIIUTI A-23 IS1 B9 11 2Ell-1 RHR-240-R-2 PIPE TO ELBOW AUG 1 El 1 om PRE B J H2 2E11-1 RHR-24B-R-3 ISIIUTI A-23 IS1 89 11 2Ell-1 RHR-24B-R-3 ELBOW TO PIPE AIJG 1 El 1 om PRE B J H2 2E11-1 RHR-240-R-4 A-23 IS1 89.1 1 2E11-1 RHR-240-R-4 PIPE TO ELBOW AUG 1 El I om PRE B J H2 2E11-1 RHR-24B-R-5 ISIIUTI A-23 IS1 89.1 1 2Ell-1 RHR-240-R-5 ELBOW TO PIPE AIJG 1 El I om PRE B J H2 2E11-1 RHR-248-R-6A A-23 IS1 89.1 1 2Ell-1 RHR-240-R-6A PIPE TO RED AIJG 1 El I om PRE B J H2 2E11-1 RHR-24B-R-60 A-23 IS1 89.1 1 2El I -1 RHR-24B-R-60 RED TO VALVE AIJG I 1 El 1 om PRE B-J H2 2E11-1 RHR-248-R-7A A-23 IS1 89.1 1 2Ell-1 RHR-240-R-7A VALVE TO RED AIJG 1 El I om PRE B-J H2 2E11-1 RHR-240-R-70 A-23 IS1 89 11 2Ell-1 RHR-240-R-70 RED TO PIPE AUG 1 El 1 om PRE BJ H2 2E11-1 RHR-24B-R-8 A-23 IS1 89.1 1 2Ell-1 RHR-240-R-8 PIPE TO VALVE AIJG 1 El 1 om PRE r 2 5 ------------ - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - --------- - - - - -------- - - - - ------------ - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----------- - - - - - - - - - - - - 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ND 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - S-- - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Page 22 - 30 Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc.

Code Case Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure B J H2 2E11-1 RHR-24B-R-9 ISIIUTINMP-ES-024-502 A-23 IS1 89.1 1 2E11-1 RHR-24B-R-9 VALVE TO PIPE AUG 1 El 1 ow PRE B J H2 2E11-1 RHR-9A-HS-1 ISIIUTI A-20 IS1 89.1 1 2Ell-1 RHR-9A-HS-1 2N6A AUG 1 El 1 ow PRE B J H2 2E11-1 RHR-9B-HS-1 A-20 IS1 B9.11 2Ell-1 RHR-9B-HS-1 2N6B AUG 1 El 1 OWN PRE B J H2 2E21-1 CS-IOA-1 ISIIRTI A-24 IS1 89.1 1 2E21-1 CS-10A-1 VALVE TO PIPE AUG 1 E21 ow PRE B-J H2 2E21-1 CS-IOA-10 ISIIUTI A-24 IS1 89.1 1 2E21-1 CS-10A-10 ELBOW TO PIPE AUG 1 E21 ow PRE B J H2 2E21-1 CS-IOA-11 A-24 IS1 89.1 1 2E21-1 CS-10A-11 PIPE TO VALVE AUG 1 E21 ow PRE B J H2 2E21-1 CS-1 OA-12 A-24 IS1 2E21-1 CS-10A-12 VALVE TO PIPE AUG B9.11 1 E21 ow PRE B J H2 2E21-1 CS-IOA-13 ISIIUTI A-24 IS1 2E21-1 CS-10A-13 PIPE TO ELBOW AUG 89.1 1 1 E21 ow PRE B-J H2 2E21-1 CS-1 OA-14 A-24 IS1 2E21-1 CS-10A-14 ELBOW TO PIPE AUG 89.1 1 1 E21 ow PRE H2 2E21-1 CS-10A-15 A-24 IS1 B-J 2E21-1 CS-10A-15 PIPE TO ELBOW AUG 89.1 1 1 E21 ow PRE Period 1 m o 2 &? 5 5 s - - - - - - - - - - - - - - - ----s--- - - - - - - - - - -- - - ------- - - - - - - - - ---- - - - - - - - - - - - - ------- - - - - - - - - - - - - ------- - - - - - - - - - - - - ------- - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - Period 2 7 2 I CY - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - - - -

4 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 23 - 30 711 312006 1 Period 1 Period 2 Period 3 (Y C) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. IternNO, Cornp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case 6 J H2 2E21-1 CS-10A-16 A-24 IS1 8911 2E21-1 CS-10A-16 ELBOW TO PIPE AUG 1 E21 om pRE B-J H2 2E21-1 CS-1 OA-17 A-24 IS1 89 11 2E21-1 CS-10A-17 PIPE TO ELBOW AUG 1 E21 om PRE B-J H2 2E21-1 CS-IOA-18 ISIIUTINMP-ES-024502 A-24 IS1 89.1 1 2E21-1 CS-10A-18 ELBOW TO ELBOW AUG 1 E2 1 PRE B-J H2 2E21-1CS-10A-19 A-24 IS1 89.1 1 2E21-1 CS-10A-19 ELBOW TO PIPE AUG 1 E21 om PRE B-J H2 2E21-1 CS-1 OA-2 A-24 IS1 89.1 1 2E21-1 CS-10A-2 PIPE TO ELBOW AUG 1 E21 OWN PRE B-J H2 2E21-1 CS-10A-20 ISIIUTI A-24 IS1 89.1 1 2E21-1 CS-10A-20 END AUG 1 E21 om PRE B-J H2 2E21-1 CS-1 OA-3 A-24 IS1 89.1 1 2E21-1 CS-10A-3 ELBOWTO VALVE AUG 1 E21 om PRE 6-J H2 2E21-1 CS-IOA-4 A-24 IS1 89.1 1 2E21-1 CS-10A-4 VALVE TO PIPE AUG 1 E21 ow PRE 6-J H2 2E21-1 CS-1 OA-4A A-24 IS1 8911 2E21-1CS-10A-4A PIPE TO ELBOW AUG 1 E21 om PRE B-J H2 2E21-1 CS-1 OA-5 ISIIUTINMP-ES-024502 A-24 IS1 8911 2E21-1 CS-10A-5 ELBOW TO PIPE AUG 1 E21 OWN PRE O) o ?i 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 -----------. - - - - - - - - - - - - ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - -

Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2E21-1 CS-1 0A-5A A-24 IS1 89.11 2E21-1 CS-1 0A-5A PIPE TO PENETRATION AUG 1 E2 1 OWN PRE B J H2 2E21-1 CS-1OA-6 A-24 IS1 89.11 2E21-1 CS-10A-6 PIPE TO ELBOW AUG 1 E2 1 OWN PRE B J H2 2E21-1 CS-1 OA-7 A-24 ISI 89.1 1 2E21-1 CS-10A-7 ELBOW TO PIPE AUG 1 E21 OWN PRE B J H2 2E21-1 CS-10A-8 A-24 IS1 B9.11 2E21-1 CS-10A-8 PIPE TO VALVE AUG 1 E2 1 OWN PRE B J H2 2E21-1 CS-1 OA-9 A-24 IS1 89.11 2E21-1 CS-10A-9 VALVE TO ELBOW AUG 1 E2 1 OWN PRE B J H2 2E21-1 CS-108-1 A-25 IS1 89.11 2E21-1 CS-10B-1 VALVE TO PIPE AU G 1 E21 OWN PRE B J H2 2E21-1 CS-1 OB-10 A-25 IS1 PlPE TO VALVE AUG OWN PRE B J H2 2E21-1 CS-100-11 A-25 IS1 VALVE TO PlPE AU G OWN PRE B J H2 2E21-1 CS-IOB-12 A-25 IS1 89.1 1 2E21-1 CS-10B-12 PIPE TO ELBOW AUG 1 E21 OWN PRE B-J H2 2E21-1 CS-1 OB-13 A-25 IS1 B9.11 2E21-1 CS-10B-13 ELBOW TO PIPE AUG 1 E21 OWN PRE Page 24 - 30 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2E21-1 CS-100-14 lSllUT1 A-25 IS1 89.1 1 2E21-1 CS-108-14 PIPE TO ELBOW AUG 1 E21 OWN PRE F Period 1 B J H2 2E21-1 CS-100-15 A-25 IS1 - - - - 89.1 1 2E21-1 CS-100-15 ELBOW TO PIPE AUG - - - - 1 E21 OWN ---- PRE - - - - B J H2 2E21-1 CS-100-16 A-25 IS1 89.1 1 2E21-1 CS-108-16 PIPE TO ELBOW AUG 1 E21 OWN PRE B J H2 2E21-1 CS-100-17 A-25 IS1 89 11 2E21-1 CS-108-17 ELBOW TO ELBOW AUG 1 E21 OWN PRE B-J H2 2E21-1 CS-100-18 A-25 IS1 89 11 2E21-1 CS-108-18 ELBOW TO PIPE AUG 1 E21 OWN PRE B J H2 2E21-1 CS-100-19 ISIIUTI A-25 IS1 89.1 1 2E21-1 CS-108-19 END AUG 1 E21 OWN PRE B J H2 2E21-1 CS-100-2 ISllUTl A-25 IS1 89.1 1 2E21-1 CS-108-2 PIPE TO VALVE AUG 1 E21 OWN PRE B J H2 2E21-1 CS-100-3 A-25 IS1 89.1 1 2E21-1 CS-108-3 VALVE TO PIPE AUG 1 E21 OWN PRE Period 2 - - - - - - - - ---- - - - - - - - - - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - B J H2 2E21-1 CS-100-4 lSllUT1 A-25 IS1 89.1 1 2E21-1 CS-108-4 PIPE TO PENETRATION AUG 1 E21 OWN PRE B J H2 2E21-1 CS-100-5 A-25 IS1 89.1 1 2E21-1 CS-108-5 PIPE TO ELBOW AUG 1 E21 OWN PRE Period 3 ---- - - - - ---- - - - - - - - - - - - - ---- - - - -

Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2E21-1 CS-1OB-6 A-25 IS1 89.1 1 2E21-1 CS-10B-6 ELBOW TO PIPE AUG 1 E21 OWN PRE B J H2 2E21-1 CS-1OB-7 A-25 IS1 89.11 2E21-1 CS-10B-7 PIPE TO VALVE AUG 1 E21 OWN PRE B J H2 2E21-1 CS-1OB-8 A-25 IS1 89.1 1 2E21-1 CS-10B-8 VALVE TO ELBOW AUG 1 E21 OWN PRE B J H2 2E21-1 CS-1 OB-9 A-25 IS1 89.11 2E21-1 CS-10B-9 ELBOW TO PIPE AUG 1 E21 OWN PRE B J H2 2E41-1 HPCI-10-D-1 lSllUT1 A-26 IS1 89.1 1 2E41-1 HPCI-10-0-1 BRANCH CONNECTION TO ELBOW AUG 1 E4 1 OWN PRE B J H2 2E41-1 HPCI-10-D-10 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-10 ELBOW TO PIPE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-11 A-26 IS1 89.1 1 2E41-1 HPCI-10-0-11 PIPE TO PIPE AUG 1 E41 OWN PRE BJ H2 2E41-1 HPCI-10-D-12 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-12 PIPE TO ELBOW AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-13 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-13 ELBOW TO PIPE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-14 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-14 PIPE TO TEE AU G 1 E4 1 OWN PRE Page 26 - 30 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method 1 Procedure Code Case B J H2 2E41-1 HPCI-10-D-15 lSllUT1 A-26 IS1 89 11 2E41-1 HPCI-10-D-15 TEE TO PIPE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-16 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-16 PIPE TO CAP AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-17 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-17 TEE TO PIPE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-18 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-18 PIPE TO VALVE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-19 ISIIUTI A-26 IS1 89.1 1 2E41-1 HPCI-10-D-19 AUGIUTI VALVE TO PIPE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-2 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-2 ELBOW TO PIPE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-20 ISIIUTI A-26 IS1 89.1 1 2E41-1 HPCI-10-D-20 AUGIUTI PIPE TO PENETRATION AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-21 ISIIUTI A-26 IS1 89.11 2E41-1 HPCI-10-D-21 AUGIUTI PENETRATION TO PIPE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-22 ISllUTlNMP-ES-024-502 A-26 IS1 89.11 2E41-1 HPCI-10-D-22 AUGIUTINMP-ES-024-502 PIPE TO VALVE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-3 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-3 PIPE TO ELBOW AUG 1 E41 OWN PRE Period 1 age 27 - 30 711312006 1 Period 2 Period 3 NO I, A Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-J H2 2E41-1 HPCI-10-D-4 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-4 ELBOW TO PIPE AUG 1 E41 OWN PRE B-J H2 2E41-1 HPCI-1 O-D-5 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-5 PIPE TO ELBOW AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-6 A-26 IS1 89.1 1 2E41-1HPCI-10-D-6 ELBOW TO PIPE AUG 1 E41 OWN PRE B 4 H2 2E41-1 HPCI-10-D-7 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-7 PIPE TO ELBOW AUG 1 E41 OWN PRE B -J H2 2E41-1 HPCI-1 O-D-8 A-26 IS1 89.1 1 2E41-1 HPCI-10-D-8 ELBOW TO PIPE AUG 1 E41 OWN PRE B J H2 2E41-1 HPCI-10-D-9 lSllUT1 A-26 IS1 89.11 2E41-1 HPCI-10-D-9 PIPE TO ELBOW AUG 1 E41 OWN PRE B-J H2 2E51-1 RCIC-4D-1 ISllUTi A-27 IS1 89.1 1 2E51-1 RCIC-4-D-1 BRANCH CONNECTION TO PIPE AUG 1 E51 OWN PRE B J H2 2E51-1 RCIC-4-D-10 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-10 PIPE TO TEE AUG 1 E51 OWN PRE B-J H2 2E51-1 RCIC-CD-11 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-11 TEE TO PIPE AUG 1 E5 1 OWN PRE B J H2 2E51-1 RCIC-4-D-12 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-12 PIPE TO CAP AUG 1 E51 OWN PRE Period 1 Period 2 .? 2 5 Period 3 Revision:

1 Category, ItemNO, HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H2 2E51-1 RCIC-4-D-13 A-27 IS1 89.1 1 2E51-1 RCIC-4-0-13 TEE TO PIPE AUG 1 E5 1 OWN PRE B J H2 2E51-1 RCIC-4-D-14 A-27 IS1 B9 11 2E51-1 RCIC-4-D-14 PIPE TO PIPE AUG 1 E5 1 OWN PRE B-J H2 2E51-1 RCIC-4D-15A A-27 IS1 89.1 1 2E51-1 RCIC-4-D-15A PIPE TO VALVE AUG 1 E51 OWN PRE B J H2 2E51-1 RCIC-4-D-1 6A ISllUTlNMP-ES-024502 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-16A AUGIUTINMP-ES-024-502 VALVE TO PENETRATION AUG 1 E51 OWN PRE B J H2 2E51-1 RCIC-4D-17 ISIIUTI A-27 IS1 89.1 1 2E51-1 RCIC-4-D-17 AUGIUTI PENETRATION TO ELBOW AUG 1 E5 1 OWN PRE B J H2 2E51-1 RCIC-4D-18 AUGIUTI A-27 IS1 89.1 1 2E51-1 RCIC-4-D-18 ELBOW TO PIPE AUG 1 E5 1 OWN PRE B J H2 2E51-1 RCIC-4-D-1 9A ISIIUTI A-27 IS1 89.1 1 2E51-1 RCIC-4-D-19A AUGIUTI PIPE TO VALVE AUG 1 E5 1 OWN PRE B J H2 2E51-1 RCIC-4D-2 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-2 PIPE TO ELBOW AUG 1 E5 1 OWN PRE B J H2 2E51-1 RCIC-4D-3 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-3 ELBOW TO PIPE AUG 1 E5 1 OWN PRE B-J H2 2E51-1 RCIC-4-D-4 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-4 PIPE TO ELBOW AUG 1 E5 1 OWN PRE P Period 1 m o & 2 5 5 ---- ---- ---- ---- - - - - ---- - - - - - - - - jge 29 - 30 Period 2 1 1- - - - ---- ---- ---- 711312006 1 Period 3 ICY (3 2 2 5 5 - - - - - - - - ---- - - - -

3 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 30 - 30 711312006 1 Period 1 Period 2 Period 3 N o 2 2 I, I, - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - Category, Iso No. IternNO, Comp. Desc.

Class Summary I ComplD I System Scope 1 Method 1 Procedure Code Case B J H2 2E51-1 RCIC-4-D-5 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-5 ELBOW TO PIPE AUG 1 E51 om PRE B J H2 2E51-1 RCIC-4-D-6 lSllUT1 A-27 IS1 69.1 1 2E51-1 RCIC-4-D-6 PIPE TO ELBOW AUG 1 E5 1 om PRE 6 J H2 2E51-1 RCIC-4-D-7 A-2 7 IS1 89.1 1 2E51-1 RCIC-4-D-7 ELBOW TO PIPE AUG 1 E51 om PRE B-J H2 2E51-1 RCIC-4-D-8 A-27 IS1 89.1 1 2E51-1 RCIC-4-D-8 PIPE TO ELBOW AuG 1 E51 om PRE B-J H2 2E51-1 RCIC-4-D-9 A-27 IS1 89 11 2E51-1 RCIC-4-D-9 ELBOW TO PIPE AUG 1 E51 om PRE m o z 2 I, 5 - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 I, ------------ - - - - -------- - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - --------- - - - -

Y Revision:

1 Category, ItemNO, w HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Cornp. Desc.

Class Summarv I ComalD I Svstem Scope / Method I Procedure Code Case B9 40 2B31-1 RC-2A BC TO PIPE AUG 1 831 OWN PRE NB-J H2 2831 -1 RC-2A-10 A-16A IS1 B9 40 2B31-1 RC-2A-10 PIPE TO VALVE AUG 1 831 OWN PRE NB J H2 2831-1 RC-2A-2 ISIIPTI A-16A IS1 B9 40 2B31-1 RC-2A-2 PIPE TO ELBOW AUG 1 831 OWN PRE NB-J H2 2831 -1 RC-2A-3 ISIIPTI A-16A IS1 B9 40 2B31-1 RC-2A-3 ELBOW TO PIPE AUG 1 831 OWN PRE NB J H2 2831 -1 RC-2A-4 A-16A IS1 B9 40 2B31-1 RC-2A-4 PIPE TO ELBOW AUG 1 831 OWN PRE NB J H2 2831-1 RC-2A-5 A-16A IS1 B9 40 2B31-1 RC-2A-5 ELBOW TO PIPE AUG 1 831 OWN PRE NB-J H2 2B31-1 RC-2A-6 A-16A IS1 B9 40 2B31-1 RC-2A-6 PIPE TO ELBOW AUG 1 831 OWN PRE NB J H2 2B31-1 RC-2A-7 A-I 6A IS1 B9 40 2B31-1 RC-2A-7 ELBOW TO PIPE AUG 1 831 OWN PRE NB J H2 2831-1 RC-2A-8 A-16A IS1 89 40 2B31-1 RC-2A-8 PIPE TO VALVE AUG 1 831 OWN PRE . . .- NB J H2 2831-1 RC-2A-9 A-16A IS1 89.40 2B31-1 RC-2A-9 VALVE TO PIPE AUG 1 831 OWN PRE Page 1 - 16 Period 1 Period 2 Period 3 Revision:

1 Category, ItemNO, HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company lso No. Comp. Desc.

Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case NB J H2 2831 -1 RC-2B-1 A-1 6A IS1 BC TO PIPE AUG OWN PRE NB J H2 2831 -1 RC-28-10 A-1 8A IS1 89.40 2831 -1 RC-28-10 PIPE TO VALVE AUG 1 83 1 OWN PRE NB J H2 2B31-1 RC-2B-11 A-1 8A IS1 89.40 2831 -1 RC-28-11 VALVE TO PIPE AUG 1 83 1 OWN PRE NB J H2 2831-1 RC-2B-12 A-1 8A IS1 89.40 2B31-1 RC-2B-12 PIPE TO VALVE AUG 1 83 1 OWN PRE NB J H2 2831 -1 RC-2B-2 A-1 8A IS1 89.40 2B31-1 RC-28-2 PIPE TO ELBOW AUG 1 831 OWN PRE NB J H2 2831-1 RC-2B-3 A-1 8A IS1 89.40 2831 -1 RC-28-3 ELBOW TO PIPE AUG 1 831 OWN PRE NB-J H2 2831 -1 RC-2B-4 A-1 8A IS1 89.40 2B31-1 RC-28-4 PIPE TO ELBOW AUG 1 831 OWN PRE NB J H2 2831 -1 RC-2B-5 ISIIPTI A-1 8A IS1 89.40 2831-1 RC-2B-5 ELBOW TO PIPE AUG 1 83 1 OWN PRE NB J H2 2831-1 RC-28-6 ISIIPTI A-1 8A IS1 89.40 2B31-1 RC-2B-6 PIPE TO ELBOW AUG 1 83 1 OWN PRE NB J H2 2831-1 RC-2B-7 A-1 8A IS1 89.40 2B31-1 RC-2B-7 ELBOW TO PIPE AUG 1 831 OWN PRE 3 Page 2 - 16 711 712006 ( Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 3- 16 Period 1 Period 2 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case NB J H2 2831 -1 RC-2B-8 A-18A IS1 89.40 2B31-1 RC-28-8 PIPE TO ELBOW AUG 1 831 OWN PRE NB-J H2 2831 -1 RC-2B-9 A-18A IS1 89.40 2831-1 RC-2B-9 ELBOW TO PIPE AUG 1 831 OWN PRE NB J H2 2831-1 RC-2DR-1 A-28A IS1 89.21 2831-1 RC-2DR-1 SAFE-END TO NOZZLE AUG 1 831 OWN PRE NB-J H2 2831 -1 RC-2DR-10 ISIIPTI A-28A IS1 89.40 2B31-1 RC-2DR-10 PIPE TO ELBOW AUG 1 831 OWN PRE NB J HZ 2831-1 RC-2DR-11 lSllPT1 A-28A IS1 89.40 2831-1 RC-2DR-11 ELBOW TO PIPE AUG 1 831 OWN PRE NB J H2 2831 -1 RC-2DR-12 A-28A IS1 89.40 2B31-1 RC-2DR-12 PIPE TO ELBOW AUG 1 831 OWN PRE NB J H2 2831-1 RC-2DR-13 A-28A IS1 89.40 2B31-1 RC-2DR-13 ELBOW TO PIPE AUG 1 831 OWN PRE NB J H2 2831-1 RC-2DR-14 A-28A IS1 89.40 2B31-1 RC-2DR-14 PIPE TO ELBOW AUG 1 831 OWN PRE NB J H2 2831 -1 RC-2DR-15 ISIIPTI A-28A IS1 89.40 2B31-1 RC-2DR-15 ELBOW TO PIPE AUG 1 831 OWN PRE NB J HZ 2831-1 RC-2DR-16 ISllPTl A-28A IS1 89.40 2B31-1 RC-2DR-16 PIPE TO TEE AUG 1 831 OWN PRE Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope 1 Method I Procedure Code Case NBJ H2 2831-1 RC-2DR-17 A-28A IS1 89.40 2B31-1RC-2DR-17 TEE TO PIPE AUG 1 831 OWN PRE NBJ HZ 2831-1 RC-2DR-18 A-28A IS1 89.40 2831 -1RC-2DR-18 PIPE TO VALVE AUG 1 831 OWN PRE NBJ H2 2831-1 RC-2DR-19 A-28A IS1 89.40 2B31-1 RC-2DR-19 VALVE TO PIPE AU G 1 831 OWN PRE NB-J H2 2B31-1 RC-2DR-1 A A-28A IS1 89.21 2B31-1 RC-2DR-1 A NOZZLE TO SAFE-END AUG 1 83 1 OWN PRE NBJ H2 2831-1 RC-2DR-2 A-28A IS1 89.40 2831 -1 RC-2DR-2 PIPE TO ELBOW AUG 1 831 OWN PRE NB-J H2 2831-1 RC-2DR-20 A-28A IS1 B9.40 2B31-1 RC-2DR-20 PIPE TO VALVE AUG 1 B3 1 OWN PRE NB J HZ 2831-1 RC-2DR-21 A-28A IS1 B9.40 2B31-1 RC-2DR-21 TEE TO PIPE AUG 1 831 OWN PRE NBJ HZ 2831 -1 RC-2DR-3 A-28A IS1 B9.40 2B31-1 RC-2DR-3 ELBOW TO PIPE AUG 1 831 OWN PRE NBJ H2 2B31-1 RC-2DR-4 ISIIPTI A-28A IS1 89.40 2831 -1 RC-2DR-4 PIPE TO PIPE AUG 1 831 OWN PRE NB J H2 2B31-1 RC-2DR-5 A-28A IS1 PlPE TO ELBOW AUG OWN PRE Period 1 Period 2 I Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 5 - 16 711 712006 1 Period 1 Period 2 Period 3 CY rn 2 2 5 5 - - - - ---- - - - - - - - - ---- - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - ----- ----- .- 2 5 ------------ - - - - -------- - - - - ------------ - - - - -------- - - - - ------------ - - - - -------- - - - - ------------ - - - - - - - - - - - - ------------ - - - - -------- - - - - -s---------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - -----------

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Category, Iso No. IternNO, Cornp. Desc.

Class Summary I CornplD I System Scope I Method I Procedure Code Case NBJ H2 2831 -1 RC-2DR-6 A-28A IS1 89.40 2B31-1 RC-2DR-6 ELBOW TO PIPE AUG 1 83 1 om PRE NB J H2 2831 -1 RC-2DR-7 A-28A IS1 89.40 2831 -1 RC-2DR-7 PIPE TO TEE AUG 1 831 om PRE NB J H2 2B31-1 RC-2DR-8 A-28A IS1 89.40 2B31-1 RC-2DR-8 TEE TO REDUCING INSERT AUG 1 831 om PRE NB J H2 2831-1 RC-2DR-8A A-28A IS1 89.40 2B31-1 RC-2DR-8A REDUCING INSERT TO TUBING AUG 1 83 1 om PRE NB-J H2 2831-1 RC-2DR-9 A-28A IS1 89.40 2831 -1 RC-2DR-9 '4 4 TEE TO PIPE AUG 1 83 1 om PRE NB J H2 2C41-1 SBLC-1.5-1 lSllPT1 A-39 IS1 89.40 2C41-1 SBLC-1.5-1 VALVE TO PIPE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-10 ISllPTl A-39 IS1 89.40 2C41-1 SBLC-1.5-10 PIPE TO ELBOW AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-11 ISIIPTI A-39 IS1 89.40 2C41-1 SBLC-1.5-11 ELBOW TO PIPE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-12 A-39 IS1 89.40 2C41-1 SBLC-1.5-12 PIPE TO ELBOW AUG 1 C41 om PRE NB-J H2 2C41-1 SBLC-1.5-13 A-39 IS1 89.40 2C41-1SBLC-1 5-13 ELBOW TO PIPE AUG 1 C41 OWN PRE % w w ?i ?i - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - ------- -------

V Revision:

1 C HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company u Page 6 - 16 711 712006 1 Period 1 Period 2 Period 3 NW 2 2 i5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----- - - - - - - - - - - - - - - - - Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case NB J H2 2C41-1 SBLC-1.5-14 A-39 IS1 89.40 2C41-1 SBLC-1.5-14 PIPE TO VALVE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-15 A-39 IS1 89.40 2C41-1 SBLC-1.5-15 VALVE TO ELBOW AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-16 A-39 IS1 89.40 2C41-1SBLC-1.5-16 ELBOW TO PIPE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-17 A-39 IS1 89.40 2C41-1 SBLC-1.5-17 PIPE TO TEE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-18 A-39 IS1 89.40 2C41-1 SBLC-1.5-18 TEE TO PIPE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-19 A-39 IS1 89.40 2C41-1 SBLC-1.5-19 PIPE TO PIPE AUG 1 C41 om PRE NB-J H2 2C41-1 SBLC-1.5-2 ISIIPTI A-39 IS1 89.40 2C41-1 SBLC-1.5-2 PIPE TO TEE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-20 A-39 IS1 89.40 2C41-1 SBLC-1.5-20 PIPE TO VALVE AUG 1 C41 om pRE NB J H2 2C41-1 SBLC-1.5-21 A-39 IS1 89.40 2C41-1 SBLC-1.5-21 VALVE TO PIPE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-22 A-39 IS1 PIPE TO ELBOW AUG 89.40 2C41-1 SBLC-1.5-22 1 C41 om PRE O) o z 2 5 5 - - - - - - - - - - - - - - - - - - - - - ; - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - F 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -s---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - _________--- - - - - - - - - - - - -

Revision:

1 HNP-2 Fourth Interval Class 1 1SI Plan Southern Nuclear Operating Company Period 1 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case NB J H2 2C41-1 SBLC-1.5-23 A-39 IS1 89.40 2C41-1 SBLC-1.5-23 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-24 lSllPT1 A-39 IS1 89.40 2C41-1 SBLC-1.5-24 PIPE TO ELBOW AUG 1 C41 OWN PRE NB-J H2 2C41-1 SBLC-1.5-25 ISIIPTI A-39 IS1 09.40 2C41-1 SBLC-1.5-25 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-26 A-39 IS1 89.40 2C41-1 SBLC-1.5-26 PIPE TO ELBOW AU G 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-27 A-39 IS1 89.40 2C41-1 SBLC-1.5-27 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-28 lSllPT1 A-39 IS1 89.40 2C41-1 SBLC-1.5-28 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-29 ISIIPTI A-39 IS1 89.40 2C41-1 SBLC-1.5-29 ELBOWTO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-3 A-39 IS1 TEE TO PlPE AUG OWN PRE NB J H2 2C41-1 SBLC-1.5-30 A-39 IS1 89.40 2C41-1 SBLC-1.5-30 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-31 A-39 IS1 89.40 2C41-1SBLC-1.5-31 ELBOW TO PIPE AUG 1 C41 OWN PRE Period 2 .- 2 5 Period 3 I Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Period 1 Category, ItemNO, Iso No. Comp. Desc. Class Summary 1 ComplD I System Scope I Method I Procedure code Case NB-J HZ 2C41-1 SBLC-1.5-32 A-39 IS1 89.40 2C41-1 SBLC-1.5-32 PIPE TO INSERT AUG 1 C41 OWN PRE NB J HZ 2C41-1 SBLC-1.5-33 A-39 IS1 89.40 2C41-1 SBLC-1.5-33 INSERT TO PIPE AUG 1 C41 OWN PRE NB J HZ 2C41-1SBLC-1.5-34 A-39 IS1 89.40 2C41-1 SBLC-1.5-34 PIPE TO ELBOW AUG 1 C41 OWN PRE NB-J HZ 2C41-1 SBLC-1.5-35 A-39 IS1 89.40 2C41-1 SBLC-1.5-35 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-36 A-39 IS1 89.40 2C41-1 SBLC-1.5-36 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-37 A-39 IS1 ELBOWTO PlPE AUG OWN PRE PlPE TO ELBOW AUG OWN PRE NB J HZ 2C41-1 SBLC-1.5-39 A-39 IS1 89.40 2C41-1 SBLC-1.5-39 ELBOWTO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-4 A-39 IS1 89.40 2C41-1 SBLC-1.5-4 PIPE TO PIPE AUG 1 C41 OWN PRF . . .- NB J H2 2C41-1 SBLC-1.5-40 ISlIPTl A-39 IS1 89.40 2C41-1 SBLC-1.5-40 PIPE TO ELBOW AUG 1 C41 OWN PRE 'age 8- 16 Period 2 Period 3 Revision:

1 Category, ItemNO, HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case NB J H2 2C41-1 SBLC-1.5-41 ISIIPTI A-39 IS1 89.40 2C41-1 SBLC-1.5-41 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-42 A-39 IS1 89.40 2C41-1 SBLC-1.5-42 PIPE TO INSERT AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-43 A-39 IS1 89.40 2C41-1SBLC-1.5-43 INSERT TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-44 A-40 IS1 B9.40 2C41-1 SBLC-1.5-44 PIPE TO ELBOW AUG 1 C4 1 OWN PRE NBJ H2 2C41-1 SBLC-1.5-45 A-40 IS1 89.40 2C41-1SBLC-1.5-45 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-46 A-40 IS1 89.40 2C41-1SBLC-1.5-46 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-47 A-40 IS1 89.40 2C41-1 SBLC-1.5-47 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-48 A-40 IS1 89.40 2C41-1 SBLC-1.5-48 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-49 A-40 IS1 89.40 2C41-1 SBLC-1.5-49 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-5 A-39 IS1 89.40 2C41-1 SBLC-1.5-5 PIPE TO ELBOW AUG OWN PRE Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 10 - 16 711 712006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case NB J H2 2C41-1 SBLC-1.5-50 ISIIPTI A-40 IS1 89.40 2C41-1 SBLC-1.5-50 PlPE TO ELBOW AUG 1 C41 om PRE NB-J H2 2C41-1 SBLC-1.5-51 ISIIPTI A-40 IS1 89.40 2C41-1 SBLC-1.5-51 ELBOW TO PIPE AUG 1 C41 om PRE NBJ H2 2C41-1 SBLC-1.5-52 A-40 IS1 89.40 2C41-1 SBLC-1.5-52 PIPE TO TEE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-53 A-40 IS1 89.40 2C41-1 SBLC-1.5-53 TEE TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-54 A-40 IS1 89.40 2C41-1 SBLC-1.5-54 PIPE TO ELBOW AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-55 A-40 IS1 89.40 2C41-1 SBLC-1.5-55 ELBOWTO PIPE AUG 1 C41 om pRE NB J H2 2C41-1 SBLC-1.5-56 lSllPT1 A-40 IS1 89.40 2C41-1 SBLC-1.5-56 PIPE TO ELBOW AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-57 ISllPTl A-40 IS1 89.40 2C41-1 SBLC-1.5-57 ELBOWTO PIPE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-58 A-40 IS1 89.40 2C41-1SBLC-1.5-58 PIPE TO ELBOW AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-59 A-40 IS1 89.40 2C41-1 SBLC-1.5-59 ELBOW TO PIPE AUG 1 C41 om PRE N VI 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - o 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - - - - - -s---------- - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - - - - -

Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 1 - 16 711 712006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case NB J H2 2C41-1 SBLC-1.5-6 A-39 IS1 89.40 2C41-1 SBLC-1.5-6 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-60 A-40 IS1 89.40 2C41-1 SBLC-1.5-60 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-61 A-40 IS1 89.40 2C41-1 SBLC-1.5-61 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-62 lSllPT1 A-40 IS1 89.40 2C41-1 SBLC-1.5-62 PIPE TO ELBOW AUG 1 C41 OWN PRE NB-J H2 2C41-1 SBLC-1.5-63 ISIIPTI A-40 IS1 89.40 2C41-1 SBLC-1.5-63 ELBOW TO PIPE AUG 1 C41 OWN PRE NB-J H2 2C41-1 SBLC-1.5-64 ISIIPTI A-40 IS1 89.40 2C41-1 SBLC-1.5-64 PIPE TO ELBOW AUG 1 C41 OWN PRE NB-J H2 2C41-1 SBLC-1.5-65 A-40 IS1 89.40 2C41-1 SBLC-1.5-65 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-66 A-41 IS1 89.40 2C41-1 SBLC-1.5-66 PIPE TO ELBOW AUG 1 C41 OWN PRE NB-J H2 2C41-1 SBLC-1.5-67 A-41 IS1 89.40 2C41-1 SBLC-1.5-67 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-68 A-41 IS1 89.40 2C41-1 SBLC-1.5-68 PIPE TO ELBOW AUG 1 C41 OWN PRE Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 12- 16 Period 1 Period 2 711712006 1 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case NB J H2 2C41-1 SBLC-1.5-69 A-41 IS1 89.40 2C41-1 SBLC-1.5-69 ELBOW TO PIPE AUG 1 C41 OWN PRE NB-J H2 2C41-1 SBLC-1.5-7 A-39 IS1 89.40 2C41-1 SBLC-1.5-7 PIPE TO PENETRATION AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-70 ISllPTl A-41 IS1 89.40 2C41-1 SBLC-1.5-70 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-71 ISIIPTI A-41 IS1 89.40 2C41-1 SBLC-1.5-71 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-72 A-41 IS1 89.40 2C41-1 SBLC-1.5-72 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-73 A-41 IS1 89.40 2C41-1 SBLC-1.5-73 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-74 ISIIPTI A-41 IS1 89.40 2C41-1 SBLC-1.5-74 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-75 ISIIPTI A-41 IS1 89.40 2C41-1 SBLC-1.5-75 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-76 lSllPT1 A-41 IS1 89.40 2C41-1 SBLC-1.5-76 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-77 ISIIPTI A-41 IS1 89.40 2C41-1 SBLC-1.5-77 ELBOW TO PIPE AUG 1 C41 OWN PRE 3 Revision:

1 Y HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company 3 Page 13 - 16 711712006 1 Period 1 Period 2 Period 3 (Y o 2 2 I, ?i - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case NB-J H2 2C41-1 SBLC-1.5-78 A-41 IS1 89.40 2C41 -lSBLC-1.5-78 PIPE TO ELBOW AIJG 1 C41 om PRE NB-J H2 2C41-1 SBLC-1.5-79 A-41 IS1 89.40 2C41-1 SBLC-1.5-79 ELBOW TO PIPE AUG 1 C41 om PRE NB-J H2 2C41-1 SBLC-1.5-8 A-39 IS\ 89.40 2C41 -lSBLC-1.5-8 PENETRATION TO PIPE AIJG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-80 A-41 IS1 B9.40 2C41-1 SBLC-1.5-80 PIPE TO ELBOW AUG 1 C41 om PRE NB J HZ 2C41-1 SBLC-1.5-81 A-41 IS1 89.40 2C41-1 SBLC-1.5-81 ELBOW TO PIPE AUG 1 C41 om PRE NB J H2 2C41-1 SBLC-1.5-82 A-41 IS1 89.40 2'31-1 SBLC-1.5-82 PIPE TO ELBOW AUG 1 C4 1 om PRE NB J H2 2C41-1 SBLC-1.5-83 A-41 IS1 89.40 2C41-1 SBLC-1.5-83 ELBOW TO PIPE AIJG 1 C41 OWN PRE NB J H2 2C41-1 SBLC-1.5-84 A-41 IS1 89.40 2C41-1 SBLC-1.5-84 PIPE TO SAFE-END AUG 1 C41 om pRE NB J H2 2C41-1 SBLC-1.5-9 A-39 IS1 89.40 2C41-1 SBLC-1.5-9 PIPE TO PIPE AIJG 1 C41 om pRE NBJ H2 2C41-1 SBLC-2-2 ISllPTl 2-BE-3 IS1 89.21 2C41-1 SBLC-2-2 SAFE-END TO TEE AUG C41 om PRE O) o E 2 5 5 - - - - - - - - - - - - - - - - - - - - - : - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .- 2 I, ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------- - - - - -------- - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -s---------- - - - - - - - - - - - -

Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Page 14- 16 Period 2 .? 2 5 - - - - - - - - -------- - - - - ------ - - - - -------- - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case NB J H2 2G31-1 RWCU-2DR-1 lSllPT1 A-28A IS1 89.40 2G31-1 RWCU-2DR-1 PIPE TO ELBOW AUG 1 G3 1 OWN PRE NB-J H2 2G31-1 RWCU-2DR-10 ISllPTl A-28A IS1 89.40 2G31-1 RWCU-2DR-10 ELBOW TO PIPE AUG 1 G3 1 OWN PRE NB-J H2 2G31-1 RWCU-2DR-11 A-28A IS1 89.40 2G31-1 RWCU-2DR-11 PIPE TO ELBOW AUG 1 G31 OWN PRE NB-J H2 2G31-1 RWCU-2DR-12 A-28A IS1 89.40 2G31-1 RWCU-2DR-12 ELBOW TO PIPE AUG 1 G31 OWN PRE NB-J H2 2G31-1 RWCU-2DR-13 A-28A IS1 89.40 2G31-1 RWCU-2DR-13 PIPE TO ELBOW AU'G 1 G3 1 OWN PRE NB J H2 2G31-1 RWCU-2DR-14 A-28A IS1 89.40 2G31-1 RWCU-2DR-14 ELBOW TO PIPE AUG 1 G3 1 OWN PRE NB J H2 2G31-1 RWCU-2DR-15 A-28A IS1 89.40 2G31-1 RWCU-2DR-15 PIPE TO VALVE AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-16 A-28A IS1 89.40 2G31-1 RWCU-2DR-16 VALVE TO PIPE AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-17 A-28A IS1 89.40 2G31-1 RWCU-2DR-17 PIPE TO TEE AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-18 A-28A IS1 89.40 2G31-1 RWCU-2DR-18 TEE TO PIPE AUG 1 G31 OWN PRE I Period 1 ? g K W 5 5 - - - - - - - - - - - - -S - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case NB J H2 2G31-1 RWCU-2DR-19 A-28A IS1 89.40 2G31-1 RWCU-2DR-19 PIPE TO REDUCER AUG 1 G31 OWN PRE NB-J H2 2G31-1 RWCU-2DR-2 ISllPTl A-28A IS1 89.40 2G31-1 RWCU-2DR-2 ELBOW TO PIPE AUG 1 G31 OWN PRE NB-J H2 2G31-1 RWCU-2DR-20 A-28A IS1 89.40 2G31-1 RWCU-2DR-20 REDUCER TO PIPE AUG OWN PRE PlPE TO TEE AUG OWN PRE NB-J H2 2G31-1 RWCU-2DR-22 A-28A IS1 89.40 2G31-1 RWCU-2DR-22 TEE TO PIPE AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-23 A-28A IS1 89.40 2G31-1 RWCU-2DR-23 PIPE TO REDUCER AUG 1 G31 OWN PRE NB-J H2 2G31-1 RWCU-2DR-24 A-28A IS1 89.40 2G31-1 RWCU-2DR-24 REDUCER TO PIPE AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-25 ISIIPTI A-28A IS1 89.40 2G31-1 RWCU-2DR-25 PIPE TO ELBOW AUG 1 G31 OWN PRE NBJ h2 2G31-1 RWCU-2DR-26 ISIIPTI A-28A IS1 89.40 2G31-1 RWCU-2DR-26 ELBOW TO PIPE AUG 1 G31 OWN PRE PlPE TO VALVE AUG OWN PRE Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. IternNO, Cornp. Desc.

Class Summary I CornplD I System Scope 1 Method I Procedure Code Case NB J H2 2G31-1 RWCU-2DR-28 A-28A IS1 89.40 2G31-1 RWCU-2DR-28 VALVE TO PIPE AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-29 ISIIPTI A-28A 1st 89.40 2G31-1 RWCU-2DR-29 PIPE TO TEE AUG 1 G31 OWN PRE NB-J H2 2G31-1 RWCU-2DR-3 A-28A IS1 89.40 2G31-1 RWCU-2DR-3 PIPE TO ELBOW AUG 1 G31 OWN PRE 89.40 2G31-1 RWCU-2DR-4 ELBOW TO PIPE AUG 1 G31 OWN PRE NB-J H2 2G31-1 RWCU-2DR-5 A-28A IS1 89.40 2G31-1 RWCU-2DR-5 PIPE TO ELBOW AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-6 A-28A IS1 89.40 2G31-1 RWCU-2DR-6 ELBOW TO PIPE AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-7 A-28A IS1 89.40 2G31-1 RWCU-2DR-7 PIPE TO ELBOW AUG 1 G3 1 OWN PRE 89.40 2G31-1 RWCU-2DR-8 ELBOW TO PIPE AUG 1 G31 OWN PRE NB J H2 2G31-1 RWCU-2DR-9 lSllPT1 A-28A IS1 89.40 2G31-1 RWCU-2DR-9 PIPE TO ELBOW AUG 1 G31 OWN Page 16 - 16 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Category, ItemNO, Southern Nuclear Operating Company Period 1 Iso No. Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B -K H2 281 1 UC-6 ISIIMTI A-1 A IS1 81 0.1 0 281 1 UC-6 SUPPORT SKIRT AUG 1 Bl 1 N-323-1 OWN PRE B -K H2 281 1\SB1 ISIIMTI A-32 IS1 81 0.1 0 2B11 \SB1 STABILIZER BRACKET NO. 1 AUG 1 Bll OWN PRE B-K H2 281 1\SB2 ISIIMTI A-32 IS1 B1O.10 2Bll\SB2 STABILIZER BRACKET NO.

2 AUG 1 B11 OWN PRE B -K H2 281 1 \SB3 ISIIMTI A-32 IS1 81 0.1 0 2Bll \SB3 STABILIZER BRACKET NO. 3 AUG 1 B11 OWN PRE B-K H2 281 1\SB4 ISIIMTI A-32 IS1 81 0.1 0 281 1 \SB4 STABILIZER BRACKET NO. 4 AUG 1 B11 OWN PRE B -K H2 281 1 \SB5 ISIIMTI A-32 IS1 810.1 0 2Bl l\SB5 STABILIZER BRACKET NO.

5 AUG 1 B11 OWN PRE B -K H2 281 1 \SB6 ISIIMTI A-32 IS1 81 0.1 0 2B11 \SB6 STABILIZER BRACKET NO. 6 AUG 1 Bl 1 OWN PRE B-K H2 2821-1 FW-12AA-IAPL-1 THRU 8 A-10 IS1 810.20 2821-1FW-12AA-1APL-1 THRU 8 2B21 -RFW-R31 AU G 1 821 OWN PRE B-K H2 2821-1 FW-12AA-3PL-1 THRU 8 ISIIMTI A-1 0 IS1 81 0.20 2821 -1 FW-12AA-3PL-1 THRU 8 2821 -RFW-R3O AUG 1 821 OWN PRE B -K H2 2821 -1 FW-12AA-4PL-1 THRU 4 A-1 0 IS1 81 0.20 2821 -1 FW-12AA-4PL-1 THRU 4 1 821 AUG OWN PRE Page 1 - 5 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-K H2 2821-1 FW-12AB-7PL-1 THRU 4 A-1 0 IS1 810.20 2821-1 FW-12AB-7PL-1 THRU 4 2821 -RFW-HI3 AUG 1 821 OWN PRE B -K H2 2821-1 FW-12BC-7PL-1 THRU 4 A-1 1 IS1 81 0.20 2821

-1 FW-12BC-7PL-1 THRU 4 2821 -RFW-H5 AUG 1 821 OWN PRE B-K H2 2821-1 FW-12BD-IAPL-1 THRU 8 A-1 1 IS1 81 0.20 2821

-1 FW-12BD-1APL-1 THRU 8 2821 -RFW-R20 AUG 1 821 OWN PRE B -K H2 2821-1 FW-12BD-3PL-1 THRU 8 A-1 1 IS1 81 0.20 2821 -1 FW-12BD-3PL-1 THRU 8 2821 -RFW-R19 AUG 1 82 1 OWN PRE B -K H2 2821-1 FW-12BD-4PL-1 THRU 4 A-1 1 IS1 810.20 2821-1FW-12BD-4PL-1 THRU 4 2821 -RFW-HI AUG 1 821 OWN PRE B -K H2 2821 -1 MS-24A-16PL-1 THRU 4 A-6 IS1 81 0.20 2821 -1 MS-24A-16PL-1 THRU 4 T & L RESTRAINT AUG 1 821 OWN PRE B -K H2 2821 -1 MS-24A-18PS A-6 IS1 810.20 2821

-1MS-24A-18PS BELLOWS AlTACHMENT AUG 1 821 OWN PRE 8 -K H2 2821-1MS-24A-5PL-1 THRU 4 ISIIMTI A-6 IS1 810.20 2821-1MS-24A-5PL-1 THRU 4 2821 -MS-HI AUG 1 821 OWN PRE B -K H2 2821-1 MS-248-14PL-1 THRU 4 A-7 IS1 81 0.20 2821 -1 MS-248-14PL-1 THRU 4 T& L RESTRAINT AUG 1 821 OWN PRE B-K H2 2821 -1 MS-248-16PS A-7 IS1 81 0.20 2821 -1 MS-248-16PS BELLOWS AlTACHMENT AUG 1 821 OWN PRE 3 Page 2 - 5 7/14/2006 1 Period 1 Period 2 Period 3 3 Revision:

1 3 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, lso No. ItemNO, Cornp. Desc. Class Summary I CornplD I System Scope I Method l Procedure Code Case B -K H2 2821-1 MS-24B-5PL-1 THRU 4 A-7 IS1 810.20 2821-1 MS-24B-5PL-1 THRU 4 2821 -MS-H4 AUG 1 82 1 OWN PRE B -K H2 2821 -1 MS-248-8PL-1 THRU 8 A-7 IS1 81 0.20 2821 -1 MS-248-8PL-1 THRU 8 2821 -MS-R53 AUG 1 821 OWN PRE B -K H2 2821-1 MS-24C-14PL-1 THRU 4 A-8 IS1 81 0.20 2821 -1 MS-24C-14PL-1 THRU 4 T 8 L RESTRAINT AUG 1 82 1 OWN PRE 8-K H2 2821-1 MS-24C-16PS A-8 IS1 81 0.20 2821

-1 MS-24C-16PS BELLOWS ATACHMENT AUG 1 82 1 OWN PRE B -K H2 2821 -1 MS-24C-5PL-1 THRU 4 A-8 IS1 81 0.20 2821-1MS-24C-5PL-1 THRU 4 2821 -MS-H7 AUG 1 821 OWN PRE B-K H2 2821 -1 MS-24C-9PL-1 THRU 8 A-8 IS1 81 0.20 2821 -1MS-24C-9PL-1 THRU 8 2B21 -MS-R44 AUG 1 821 OWN PRF . .- B -K H2 2821-1 MS-24D-16PL-1 THRU 4 A-9 IS1 81 0.20 2821-1MS-24D-16PL-1 THRU 4 T & L RESTRAINT AUG 1 82 1 OWN PRE - B -K H2 2821-1 MS-24D-18PS A-9 IS1 81 0.20 2821 -1 MS-24D-18PS BELLOWS AUACHMENT AUG 1 821 OWN PRE B-K H2 2821 -1 MS-24D-5PL-1 THRU 4 A-9 IS1 810.20 2821-1MS-24D-5PL-1 THRU 4 2821 -MS-HI 0 AUG 1 821 OWN PRE B -K H2 2821 -1 MS-24D-9PL-1 THRU 8 A-9 IS1 81 0.20 2821-1MS-24D-9PL-1 THRU 8 2821 -MS-R37 AU G 1 821 OWN PRE Page 3 - 5 Period 1 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Period 1 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B -K H2 2831-1 RCM-28AS-5HL-1 THRU 4 A-16 IS1 810.20 2831-1 RCM-28AS-5HL-1 THRU 4 2831 -SSA-22 AUG 1 83 1 OWN PRE B -K H2 2E51-1 RCIC-4-D-7PL-1 THRU 8 ISllMTl A-27 IS1 81 0.20 2E51-1 RCIC-4-D-7PL-1 THRU 8 2E51 -RCIC-R115 AUG 1 E51 OWN PRE B-K H2 2E51-1 RCIC-4-D-9PL-1 THRU 4 A-27 IS1 810.20 2E51-1 RCIC-4-D-9PL-1 THRU 4 2E51 -RCIC-HI 12 AUG 1 E5 1 OWN PRE B-K H2 2G31-1 RWCUM-6-D-11PL-1 THRU 8 ISllPTl A-28 IS1 81 0.20 2G31-1 RWCUM-6-D-11 PL-1 THRU 8 2G31 -RWCU-H24 AUG 1 G31 OWN PRE B-K H2 2G31-1 RWCUMS-D-3PL-1 THRU 4 A-28 IS1 810.20 2G31-1 RWCUM-6-D-3PL-1 THRU 4 2G31 -RWCU-H23 AUG 1 G31 OWN PRE B -K LUG ISIIMTINMP-ES-024-401 A-4 IS1 810.30 LUG 2RC-A PUMP LUG-1 AUG 1 831 OWN PRE B -K LUG A-4 IS1 810.30 LUG 2RC-A PUMP LUG-2 AUG 1 83 1 OWN PRE B-K H2 2831URC-A PUMP LUG-3 A-4 IS1 81 0.30 2831 URC-A PUMP LUG-3 2RC-A PUMP LUG-3 AUG 1 83 1 OWN PRE B-K LUG A-4 IS1 810.30 LUG 2RC-B PUMP LUG-1 AUG 1 831 OWN PRE B -K LUG A-4 IS1 810.30 LUG 1 831 2RC-B PUMP LUG-2 AUG OWN PRE Page 4 - 5 Period 2 I T 2 I I N Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 5 - 5 711412006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B-K H2 2831PRC-8 PUMP LUG3 A-4 IS1 810.30 2831PRC-8 PUMP LUG-3 2RC-8 PUMP LUG-3 AUG 1 831 OWN PRE Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 - 1 711 712006 1 Period 1 Period 2 Period 3 Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope / Method I Procedure Code Case B-L-2 H2 2831PRC-A PUMP CASING A-4 IS1 81 2.20 2831 PRC-A PUMP CASING RC PUMP A INSIDE SURFACE AUG 1 831 om PRE B-L-2 H2 2831PRC-B PUMP CASING A-4 IS1 81 2.20 2831 PRC-8 PUMP CASING RC PUMP 8 INSIDE SURFACE AIJG 1 831 om PRE m o z 2 5 5 - - - - - - - - - - - - tt-- - - - - - - - - - - - - y 2 5 tt--t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - NO 2 2 5 5 tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - -

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1 Category, ItemNO, HNP-2 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-M-2 H2 2821-F010A BODIES A-1 2 IS1 81 2.50 2821-F010A BODIES GROUP 1 VALVE AUG 1 821 OWN PRE B-M-2 H2 2821-F01OB BODIES A-1 3 IS1 81 2.50 2821-F01OB BODIES GROUP 1 VALVE AUG 1 82 1 OWN PRE B-M-2 H2 2821-F011A BODIES A-1 2 IS1 81 2.50 2B21-F011A BODIES GROUP 2 VALVE AUG 1 82 1 OWN PRE B-M-2 H2 2821-F011 B BODIES A-1 3 IS1 81 2 50 2821-F011 B BODIES GROUP 2 VALVE AUG 1 821 OWN PRE B-M-2 H2 2821 -F013A BODIES A-5 IS1 812 50 2821 -F013A BODIES GROUP 3 VALVE AUG 1 821 OWN PRE B-M-2 H2 2821-F013B BODIES A-5 IS1 81 2.50 2821-F013B BODIES GROUP 3 VALVE AUG 1 821 OWN PR E B-M-2 H2 2821-F013C BODIES A-5 IS1 81 2 50 2B21 -F013C BODIES GROUP 3 VALVE AUG 1 821 OWN PRE B-M-2 H2 2821 -F013D BODIES A-5 IS1 81 2.50 2821-F013D BODIES GROUP 3 VALVE AUG 1 821 OWN PRE B-M-2 H2 2821-F013E BODIES A-5 IS1 81 2 50 2821 -F013E BODIES GROUP 3 VALVE AUG 1 821 OWN PR E B-M-2 H2 2821-F013F BODIES A-5 IS1 B12 50 2821-F013F BODIES GROUP 3 VALVE AUG 1 82 1 OWN PRE Period 1 Page 1 - 6 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 2 - 6 711 712006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B-M-2 H2 2821-F013G BODIES A-5 IS1 81 2 50 2B21 -F013G BODIES GROUP 3 VALVE AUG 1 821 om PRE B-M-2 H2 2B21-F013H BODIES A-5 IS1 81 2.50 2B21-F013H BODIES GROUP 3 VALVE AUG 1 B21 om PRE B-M-2 H2 2821 -F013K BODIES A-5 IS1 B12.50 2821 -F013K BODIES GROUP 3 VALVE AUG 1 821 om PRE B-M-2 H2 2B21-F013L BODIES A-5 IS1 81 2.50 2821 -F013L BODIES GROUP 3 VALVE AUG 1 821 om PRE B-M-2 H2 2821-F013M BODIES A-5 IS1 81 2.50 2821 -F013M BODIES GROUP 3 VALVE AuG 1 821 om PRE B-M-2 H2 2821 -F022A BODIES A-6 IS1 B12.50 2821 -F022A BODIES GROUP 4 VALVE AUG 1 B21 om PRE B-M-2 H2 2B21-F022B BODIES A-7 IS1 B12.50 2821 -F022B BODIES GROUP 4 VALVE AUG 1 B21 om PRE B-M-2 H2 2B21-F022C BODIES A-8 IS1 81 2.50 2821 -F022C BODIES GROUP 4 VALVE AUG 1 B21 om PRE B-M-2 H2 2B21-F022D BODIES A-9 IS1 B12.50 2821 -F022D BODIES GROUP 4 VALVE AUG 1 821 om PRE B-M-2 H2 2821 -F028A BODIES A-6 IS1 81 2.50 2821 -F028A BODIES GROUP 4 VALVE AUG 1 821 om PRE r 2 5 t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5 5 tt-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - C) 2 2 5 5 tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 3 - 6 711 712006 1 Period 1 Period 2 Period 3 CY ~0 2 2 5 ff tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - - - - - - - - - - - - - tt-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I ~ethod I Procedure Code Case B-M-2 H2 2821-F028B BODIES A-7 IS1 81 2.50 2821 -F028B BODIES GROUP 4 VALVE AUG 1 821 om PRE B-M-2 H2 2B21-F028C BODIES A-8 IS1 81 2.50 2821 -F028C BODIES GROUP 4 VALVE AUG 1 821 om PRE B-M-2 H2 2B21-F028D BODIES A-9 IS1 81 2.50 2821-F028D BODIES GROUP 4 VALVE AUG 1 821 om PRE B-M-2 H2 2B21-F077A BODIES A-1 2 IS1 81 2.50 2821 -F077A BODIES GROUP 1 VALVE AUG 1 821 OWN PRE B-M-2 H2 2821-F077B BODIES A-1 3 IS1 81 2.50 2821 -F077B BODIES GROUP 4 VALVE AUG 1 821 om PRE B-M-2 H2 2B31-F023A BODIES A-1 6 IS1 812.50 2831-F023A BODIES GROUP 5 VALVE AUG 1 83 1 om PRE B-M-2 H2 2831-F023B BODIES A-1 8 IS1 81 2.50 2831-F023B BODIES GROUP 5 VALVE AUG 1 831 om PRE B-M-2 H2 2B31-F031A BODIES A-1 7 IS1 81 2.50 2831 -F031A BODIES GROUP 5 VALVE AUG 1 831 om PRE B-M-2 H2 2831-F031 B BODIES A-1 9 IS1 81 2.50 2831-F031 B BODIES GROUP 5 VALVE AUG 1 831 om PRE B-M-2 H2 2E11-F008 BODIES A-21 IS1 81 2.50 2E11 -F008 BODIES GROUP 6 VALVE AUG 1 El 1 om PRE Q) o 2 2 5 5 - - - - - - - - - - - - tt-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - y 2 5 tt--t--- - - - - - - - - - - - - t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t---tt-- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope I Method I Procedure Code Case B-M-2 H2 2E11-F009 BODIES A-2 1 IS1 612.50 2E11-F009 BODIES GROUP 6 VALVE AUG 1 El 1 OWN PRE B-M-2 H2 2E11-F015A BODIES A-22 IS1 B1 2.50 2E11 -F015A BODIES GROUP 7 VALVE AUG 1 El 1 OWN PRE B-M-2 H2 2E11-F015B BODIES A-23 IS1 B1 2.50 2E11 -F015B BODIES GROUP 7 VALVE AUG 1 El 1 OWN PRE B-M-2 H2 2E11-F050A BODIES A-22 IS1 81 2.50 2E11 -F050A BODIES GROUP 9 VALVE AUG 1 El 1 OWN PRE B-M-2 H2 2E11-F050B BODIES A-23 IS1 B1 2.50 2E11-F050B BODIES GROUP 9 VALVE AUG 1 El 1 OWN PRE B-M-2 H2 2E11 -F060A BODIES A-22 IS1 812.50 2E11-F060A BODIES GROUP 10 VALVE AUG 1 El 1 OWN PRE B-M-2 H2 2E11 -F060B BODIES A-23 IS1 81 2.50 2E11-F060B BODIES GROUP 10 VALVE AUG 1 El 1 OWN PRE B-M-2 H2 2E11 -F067 BODIES A-21 IS1 812.50 2E11-F067 BODIES GROUP 8 VALVE AUG 1 El 1 OWN PRE B-M-2 H2 2E21-F004A BODIES A-24 IS1 B1 2.50 2E21-F004A BODIES GROUP 11 VALVE AUG 1 E21 OWN PRE B-M-2 H2 2E21-F004B BODIES A-25 IS1 B1 2 50 2E21 -F004B BODIES GROUP 11 VALVE AUG 1 E21 OWN PRE Period 1 Page 4 - 6 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 5 - 6 711 712006 1 Period 1 Period 2 Period 3 N P) 2 2 5 5 It-- - - - - - - - - - - - - - - - - - - - - - - - - t---It-- - - - - - - - - - - - - It-- - - - - - - - - - - - - It-- - - - - - - - - - - - - It-- - - - - - - - - - - - - tt-- - - - - - - - - - - - - ti-- - - - - - - - - - - - - It-- - - - - - - - - - - - - It-- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-M-2 H2 2E21 -F005A BODIES A-24 IS1 B1 2.50 2E21 -F005A BODIES GROUP 11 VALVE AUG 1 E21 om PRE B-M-2 H2 2E21-F005B BODIES A-25 IS1 B1 2.50 2E21 -F005B BODIES GROUP 11 VALVE AUG 1 E21 om PRE B-M-2 H2 2E21-F006A BODIES A-24 IS1 812.50 2E21-F006A BODIES GROUP 13 VALVE AIJG 1 E21 om PRE B-M-2 H2 2E21-F006B BODIES A-25 IS1 B1 2.50 2E21 -F006B BODIES GROUP 13 VALVE AUG 1 E21 om pRE B-M-2 H2 2E21 -F007A BODIES A-24 IS1 B1 2.50 2E21 -F007A BODIES GROUP 12 VALVE AUG 1 E21 om PRE B-M-2 H2 2E21-F007B BODIES A-25 IS1 B1 2.50 2E21 -F007B BODIES GROUP 12 VALVE AUG 1 E21 om PRE B-M-2 H2 2E41-F002 BODIES A-26 IS1 B1 2.50 2E41 -F002 BODIES GROUP 14 VALVE AUG 1 E41 om PRE 6-M-2 H2 2E41-F003 BODIES A-26 IS1 B12.50 2E41-F003 BODIES GROUP 14 VALVE AUG 1 E41 om PRE B-M-2 H2 2G31 -Fool BODIES A-28 IS1 B1 2.50 2G31-F001 BODIES GROUP 15 VALVE AUG 1 G31 om PRE B-M-2 H2 2G31-F004 BODIES A-28 IS1 B1 2.50 2G31-F004 BODIES GROUP 15 VALVE AUG 1 G31 om PRE o) o 2 2 5 5 - - - - - - - - - - - - t - - - - - - - - - - - - tt-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - tt-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r ir" 5 tt--t--- - - - - - - - - - - - t--t---tt-- - - - - - - - - - - - - - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - I--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - - tt--t--- - - - - - - - - - - - -

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1 Category, ItemNO, HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-M-2 H2 2G31 -F027 BODIES A-28 IS1 81 2.50 2G31-F027 BODIES 1 G31 GROUP 16 VALVE AUG OWN PRE Page 6 - 6 711 712006 ( Period 1 Period 2 BH 1: 5 5 tt--t--- Period 3 Revision:

1 Category, ItemNO, Class Summary I ComplD I System HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc.

Scope I Method I Procedure Code Case 814.1 0 261 1P-02-19-1 PIPE-TO-PIPE WELD AUG 1 61 1 OWN PRE B -0 H2 281 1U-02-19-2 A-29 IS1 61 4.1 0 281 1 P-02-19-2 PIPE-TO-FLANGE WELD AUG 1 B11 OWN PRE B-0 H2 2B11 P-02-23-1 A-29 IS1 B14.10 281 1 P-02-23-1 PIPE-TO-PIPE WELD AUG 1 61 1 OWN PRE B-0 H2 281 1P-02-23-2 A-29 IS1 614.10 2B11P-02-23-2 PIPE-TO-FLANGE WELD AUG 1 B11 OWN PRE B-0 H2 281 1 P-02-27-1 A-29 IS1 B14.10 2B11 P-02-27-1 PIPE-TO-PIPE WELD AUG 1 61 1 OWN PRE B-0 H2 28 1 1 P-02-27-2 A-29 IS1 61 4.1 0 2B11P-02-27-2 PIPE-TO-FLANGE WELD AUG 1 B11 OWN PRE B -0 H2 281 1 P-02-31-1 A-29 IS1 81 4.1 0 281 1 P-02-31-1 PIPE-TO-PIPE WELD AUG 1 61 1 OWN PRE B -0 H2 2B11 P-02-31-2 A-29 IS1 614.10 2B11P-02-31-2 PIPE-TO-FLANGE WELD AUG 1 B11 OWN PRE B -0 H2 2B11 P-02-35-1 A-29 IS1 614.10 2B11P-02-35-1 PIPE-TO-PIPE WELD AUG 1 81 1 OWN PRE B -0 H2 281 1 P-02-35-2 A-29 IS1 61 4.1 0 281 1 P-02-35-2 PIPE-TO-FLANGE WELD AUG 1 B11 OWN PRE Period 1 Page 1 - 8 Period 2 Period 3 w Revision:

1 w HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company w Page 2 - 8 711 712006 1 Period 1 Period 2 Period 3 N e 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. IternNO, Cornp. Desc. Class Summary I CornplD /System Scope I Method I Procedure Code Case B -0 H2 281 1 P-06-11-1 A-29 IS1 81410 2811P-06-11-1 PIPE-TO-PIPE WELD AUG 1 81 1 om PRE B -0 H2 281 1 P-06-11-2 A-29 IS1 81410 2B11P-06-11-2 PIPE-TO-FLANGE WELD AUG 1 B11 om pRE B-0 H2 281 1P-06-15-1 A-29 IS1 814.10 281 1P-06-1 5-1 PIPE-TO-PIPE WELD AUG 1 81 1 om pRE B -0 H2 281 1 P-06-15-2 A-29 IS1 814.10 2B11P-06-15-2 PIPE-TO-FLANGE WELD AUG 1 Bll om PRE B -0 H2 281 1 P-06-39-1 A-29 IS1 81 4 10 281 1 P-06-39-1 PIPE-TO-PIPE WELD AUG 1 811 om pRE B -0 H2 281 1 P-06-39-2 A-29 IS1 81 4.1 0 281 1P-06-39-2 PIPE-TO-FLANGE WELD AUG 1 811 om pRE B -0 H2 281 1E-06-43-1 A-29 ISI 814.10 281 1P-06-43-1 PIPE-TO-PIPE WELD AUG 1 Bl 1 ow PRE B -0 H2 281 1 E-06-43-2 A-29 IS1 81 4 10 281 1 P-06-43-2 PIPE-TO-FLANGE WELD AUG 1 Bl 1 om PRE B -0 H2 281 1E-10-07-1 A-29 IS1 814.10 281 1P-10-07-1 PIPE-TO-PIPE WELD AUG 1 B11 om PRE B -0 HZ 281 1 P-10-07-2 A-29 IS1 814.10 2B11P-10-07-2 PIPE-TO-FLANGE WELD AUG 1 Bll om PRE m o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .- N P: 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - ------------ - - - - --------- - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------..----- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----------- - - - - - - - - - - - -

4 Revision:

1 3 HNP-2 Fourth Interval Class 1 IS1 Plan Page 3 - 8 711 712006 1 Southern Nuclear Operating Company Period 1 Period 2 Period 3 N o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r 2 5 --- ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - -------- - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case Q) o 2 2 i5 i5 B-0 H2 281 1 Q-10-47-1 A-29 81 4 10 281 1 Q-10-47-1 PIPE-TO-PIPE WELD AUG 1 Bl 1 ow PRE B-O H2 281 1 Q-10-47-2 A-29 IS1 81 4 10 281 1 Q-10-47-2 PIPE-TO-FLANGE WELD AUG 1 81 1 ow PRE B-O H2 281 1'2-1 4-07-1 A-29 IS1 81 4 10 281 1 Q-14-07-1 PIPE-TO-PIPE WELD AIJG 1 81 1 ow PRE B -0 H2 281 1Q-14-07-2 A-29 IS1 B14 10 281 1 Q-14-07-2 PIPE-TO-FLANGE WELD AIJG 1 811 ow PRE B -0 H2 281 1Q-14-47-1 A-29 IS1 814 10 281 1U-14-47-1 PIPE-TO-PIPE WELD AUG 1 811 ow I PRE B -0 H2 281 1Q-14-47-2 A-29 IS1 81410 2811Q-14-47-2 PIPE-TO-FLANGE WELD AIJG 1 81 1 ow PRE B -0 H2 2B11Q-18-03-1 A-29 IS1 81 4.1 0 281 1 Q-18-03-1 PIPE-TO-PIPE WELD AUG 1 81 1 ow PRE B -0 H2 281 1 Q-18-03-2 A-29 IS1 81410 2811Q-18-03-2 PIPE-TO-FLANGE WELD AIJG 1 81 1 om PRE B-O H2 2B11Q-18-51-1 A-29 IS1 814.10 281 1Q-18-51-1 PIPE-TO-PIPE WELD AUG 1 811 ow PRE B -0 H2 281 1 Q-18-51-2 A-29 IS1 814 10 2B11Q-18-51-2 PIPE-TO-FLANGE WELD AUG 1 81 1 ow pRE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

CI Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B -0 H2 281 1 U-22-03-1 A-29 IS1 81 4.1 0 281 1 U-22-03-1 PIPE-TO-PIPE WELD AUG 1 Bll OWN PRE B-0 H2 281 1 P-22-03-2 A-29 IS1 814.10 2B11U-22-03-2 PIPE-TO-FLANGE WELD AUG 1 Bll OWN PRE B-O H2 281 1 U-22-51-1 A-29 IS1 814.10 2B11P-22-51-1 PIPE-TO-PIPE WELD AUG 1 Bll OWN PRE B -0 H2 281 1 P-22-51-2 A-29 IS1 81410 2B11P-22-51-2 PIPE-TO-FLANGE WELD AUG 1 Bll OWN Period 1 PRE - - - - B -0 H2 281 1 P-26-03-1 A-29 IS1 ---- 814.10 2B11P-26-03-1 PIPE-TO-PIPE WELD AUG - - - - 1 Bll OWN ---- PRE - - - - B -0 H2 281 1 P-26-03-2 A-29 IS1 ---- 81 4.10 281 1 P-26-03-2 PIPE-TO-FLANGE WELD AUG - - - - 1 Bll OWN ---- PRE - - - - B -0 H2 281 1 P-26-51-1 A-29 IS1 ---- 81 4.1 0 281 1 U-26-51-1 PIPE-TO-PIPE WELD AUG - - - - 1 Bll OWN ---- PRE - - - - B-O H2 281 1 U-26-51-2 A-29 IS1 ---- 814.10 2B11U-26-51-2 PIPE-TO-FLANGE WELD AUG - - - - 1 B11 OWN ---- PRE - - - - B -0 H2 281 1 P-30-03-1 A-29 IS1 ---- 81 4.1 0 281 1 U-30-03-1 PIPE-TO-PIPE WELD AUG - - - - 1 Bll OWN ---- PRE - - - - B-0 H2 28 1 1 U-30-03-2 A-29 IS1 ---- 81 4.1 0 281 1 U-30-03-2 PIPE-TO-FLANGE WELD AUG - - - - 1 B11 OWN ---- PRE - - - - Page 4 - 8 Period 2 Period 3 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, lso No. ItemNO, Cornp. Desc. Class Summary 1 CornplD 1 System Scope 1 Method 1 Procedure Code Case B -0 H2 281 1P-30-51-1 A-29 IS1 814.10 2811P-30-51-1 PIPE-TO-PIPE WELD AUG 1 81 1 OWN PRE B -0 H2 281 1P-30-51-2 A-29 IS1 81410 2811P-30-51-2 PIPE-TO-FLANGE WELD AUG 1 81 1 OWN PRE B -0 H2 281 1 P-34-03-1 A-29 IS1 PIPE-TO-PIPE WELD AUG OWN PRE - B -0 H2 281 1P-34-03-2 A-29 IS1 81 4.1 0 281 1 P-34-03-2 PIPE-TO-FLANGE WELD AUG 1 81 1 OWN PRE B -0 H2 281 1P-34-51-1 A-29 IS1 PIPE-TO-PIPE WELD AUG OWN PRE B -0 H2 281 1 U-34-51-2 A-29 IS1 814.10 2811Q-34-51-2 PIPE-TO-FLANGE WELD AUG 1 81 1 OWN PRE B -0 H2 281 1P-38-07-1 A-29 IS1 814.10 281 1P-38-07-1 PIPE-TO-PIPE WELD AUG 1 81 1 OWN PRE - B -0 H2 281 1P-38-07-2 A-29 IS1 814.10 2811P-38-07-2 PIPE-TO-FLANGE WELD AUG 1 81 1 OWN PRE B -0 H2 281 1 P-38-47-1 A-29 IS1 81 4.10 281 1 U-38-47-1 PIPE-TO-PIPE WELD AUG 1 81 1 OWN PRE B -0 H2 281 1 P-38-47-2 A-29 IS1 81 4.1 0 28 1 1 P-38-47-2 PIPE-TO-FLANGE WELD AUG 1 81 1 OWN PRE Period 1 0) 0 E 2 :: :: Page 5 - 8 Period 2 I Period 3 d Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company 4 Page 6 - 8 711 712006 1 Period 1 Period 2 Period 3 CY P) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. IternNO, Cornp. Desc. Class Summary I CornplD I System Scope I Method I Procedure Code Case B -0 H2 281 1P-42-07-1 A-29 IS1 814.10 2811P-42-07-1 PIPE-TO-PIPE WELD AUG 1 B11 om pRE B -0 H2 281 1P-42-07-2 A-29 IS1 81 4.1 0 281 1 P-42-07-2 PIPE-TO-FLANGE WELD AUG 1 B11 om PRE B-0 H2 281 1 P-42-47-1 A-29 IS1 814.10 2811P-42-47-1 PIPE-TO-PIPE WELD AUG 1 B11 om PRE B -0 H2 281 1 \2-42-47-2 A-29 IS1 814.10 2B11P-42-47-2 PIPE-TO-FLANGE WELD AUG 1 81 1 om PRE B -0 H2 281 1P-46-11-1 A-29 IS1 814.10 2811P-46-11-1 PIPE-TO-PIPE WELD AUG 1 81 1 om PRE B -0 H2 281 1 P-46-11-2 A-29 IS1 814.10 2811P-46-11-2 PIPE-TO-FLANGE WELD AUG 1 Bll om PRE B-0 H2 281 1 P-46-15-1 A-29 IS1 814.10 2811U-46-15-1 PIPE-TO-PIPE WELD AUG 1 B11 om PRE B -0 H2 281 1P-46-15-2 A-29 IS1 81 4.1 0 281 1 P-46-15-2 PIPE-TO-FLANGE WELD AUG 1 B11 om PRE B -0 H2 281 1P-46-39-1 A-29 IS1 814.10 2B11P-46-39-1 PIPE-TO-PIPE WELD AUG 1 B11 om PRE B -0 H2 281 1 P-46-39-2 A-29 IS1 81 4.1 0 281 1 P-46-39-2 PIPE-TO-FLANGE WELD AUG 1 811 om PRE m o E 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 'F 2 :: ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - -

4 Revision:

1 HNP-2 Fourth Interval Class 1 IS1 Plan Page 7 - 8 7/17/2006 1 Southern Nuclear Operating Company Period 1 Period 2 Period 3 (Y o 2 2 A A - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. IternNO, Cornp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B-O H2 281 1 P-46-43-1 A-29 IS1 81 4.10 281 1P-46-43-1 PIPE-TO-PIPE WELD AUG 1 811 om PRE B -0 H2 281 1 P-46-43-2 A-29 IS1 8 1 4.1 0 28 1 1 P-46-43-2 PIPE-TO-FLANGE WELD AUG 1 811 om PRE B -0 H2 281 1 P-50-19-1 A-29 IS1 814.10 281 1P-50-19-1 PIPE-TO-PIPE WELD AUG 1 811 om PRE B -0 H2 281 1 P-50-19-2 A-29 IS1 814.10 281 1P-50-19-2 PIPE-TO-FLANGE WELD AUG 1 811 om PRE B -0 H2 281 1P-50-23-1 A-29 IS1 814.10 2811P-50-23-1 PIPE-TO-PIPE WELD AUG 1 811 om PRE B -0 H2 281 1 P-50-23-2 A-29 IS1 814.10 2811P-50-23-2 PIPE-TO-FLANGE WELD AUG 1 811 om PRE B -0 H2 281 1 P-50-27-1 A-29 IS1 814.1 0 281 1P-50-27-1 PIPE-TO-PIPE WELD AUG 1 811 .om PRE B-O H2 281 1 P-50-27-2 A-29 IS1 814.10 2811P-50-27-2 PIPE-TO-FLANGE WELD AUG 1 811 om PRE B -0 H2 281 1P-50-31-1 A-29 IS1 814.10 281 1P-50-31-1 PIPE-TO-PIPE WELD AUG 1 811 om PRE B -0 H2 281 1 P-50-31-2 A-29 IS1 814.10 2811P-50-31-2 PIPE-TO-FLANGE WELD AUG 1 811 om PRE m o E 2 A A - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,- 2 A ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -S---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - ----s------- - - - - - -- - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - -

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 1 of 33 Rev. 1 SCOPE OF EXAMINATIONS Per IWA-1400 of the Section XI Code, the Owner is responsible for determining the appropriate Code Class, for identifying the system boundaries for each class of component subject to examination, and for identifying the components exempt from examination. This requirement is met by the following:

Appropriate Code Class The determination of the appropriate Code Class for each component is made by SNC Design Organiza tion and designated on the ISI Boundary Diagrams. These Boundary Diagrams are controlled by

SNC Design Organization.

System Boundaries The system boundaries for each Code Class are designated on the ISI Boundary Diagrams.

EXAMINATION REQUIREMENTS The examination requirements for the Class 2 components identified on the Boundary Diagrams are defined in IWC-2500 for each exam ination category. Categories are:

Category C-A Pressure Retaining Welds in Pressure Vessels Category C-B Pressure Retaining Nozzle Welds in Vessels Category C-C Integral Attachments for Vessels, Piping, Pumps, and Valves Category C-F-2 Pressure Retaining Welds in Carbon or Low A lloy Steel Piping Category C-G Pressure Retaining Welds in Pumps

The following Categories are not applicable to HNP.

Category C-D Pressure Retaining Bolting Greater than 2" Diameter Category C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel or High Alloy Steel Piping Category C-G Pressure Retaining Welds in Valves

These examination requirements are not applicable to components exempt from examination per IWC-1220. Components exempt from examinati on are only subject to pressure testing requirements. (See the Exemptions Section below for more detail).

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 2 of 33 Rev. 1 EXEMPTIONS IWC-1220 defines the components that are exempt from the examination requirements of IWC-2500. Applicable Class 2 exemptions used during the 4 th Interval include:

1. Size Exemption - All components le ss than or equal to 4" in diameter and their associated supports may be exempted from examination.

2. Pressure/Temperature Exemption - All components other than RHR, Emergency Core Cooling (ECC), and Containment Heat Removal (CHR) systems that operate at a pressure <

275 psig and at a temperature <

200 0F may be exempted from examination.

3. Open Ended Exemption - Components of any si ze beyond the last shutoff valve in open ended portions of systems that do not contain water during normal operation may be exempted.

The use of these three exemptions was evaluate d and discussed below for application at HNP-2.

1. Size Exemption - For a BWR, the size exemption applie s to all Class 2 components less than or equal to 4" in diameter.

2. Pressure/Temperature Exemption - This exemption applies only to Class 2 systems or portions of systems that do not have an RHR ECC, or CHR function. The RHR, ECC, and CHR function for HNP-2 is described below.

Residual Heat Removal (RHR) Function - Per Section 5.5.7.3 of the UFSAR, portions of the RHR System are designed to remove decay and residual heat from the reactor core to achieve and maintain a cold shutdown condition. Therefore, the pressure/temperature exemption is not applied to these portions of piping.

Emergency Core Cooling (ECC) Function -

Per Section 6.3 of the UFSAR, four ECC subsystems protect the core against various sizes of hypothetical pipe breaks. Three subsystems inject emergency core cooling water into the reactor pressure vessel (RPV), and one subsystem depressurizes the RPV. The three injection subsystems are Class 2 high-pressure coolant injecti on (HPCI), Class 2 low-pressure coolant injection - LPCI mode of RHR, and Class 2 core spray (CS).

The fourth ECCS subsystem is the Class 3 automatic depressurization system. Therefore, the pressure/temperature exemption is not applied to these portions of piping.

Containment Heat Removal (CHR) Function - Per Section 6.1 of the UFSAR, the containment heat removal system consists of the shutdown cooling and the suppression pool cooling modes of the residual heat removal (RHR) system for planned and abnormal operation, as well as the core spray (CS) system and the low-pressure coolant injection (LPCI) mode of RHR for accident mitigation. Therefore, the pressure/temperature exemption is no t applied to these portions of piping.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 3 of 33 Rev. 1

3. Open Ended Exemption

The open ended exemption is applied to the following lines which normally do not contain

water. Instead, they see a nitrogen atmosphere which is not conducive to cracking. The test lines and turbine exhaust lines were not included because they are subjected to quarterly pump testing. The relief valves discharge lines were conservativel y not included because they could potentially have water in them.

Figure B RHR Containment Spray piping from 2E11-F021A through the containment spray header. Includes welds 2E11-2RHR-16A-DS-10, 11, 12, 13, 14, and

15. Figure B RHR Torus Spray piping from MO V 2E11-F027A to the top of the Torus.

Includes welds 2E11-2RHR-6A-TSP-7, 8, 9, 10, and 11. Figure B RHR Containment Spray piping from 2E11-F021B through the containment spray header. Includes welds 2E11-2RHR-16B-DS-16, 17, and 18. Figure B RHR Torus Spray piping from MO V 2E11-F027B to the top of the Torus.

Includes welds 2E11-2RHR-6B-TSP-7, 8, 9, 10, and 11. Figure B Purge and Inerting piping from MOV 2T48-F308 to the containment penetration. Includes welds 2T48-2CPI-18-PID-1, 2, and 3. Figure B Purge and Inerting piping from MOVs 2T48-F310, 2T48-F309, and 2T48-F311 to the top of the Torus. Includes welds 2T48-2CPI-20-PIT-1 through 9 and welds 2T48-2CPI-18-PIT-8&9. Figure B Purge and Inerting piping from MOV 2T48-F319 to the containment penetration. Includes welds 2T48-2CPI-18-POD-1, 2, and 3. Figure B Purge and Inerting piping from MOV 2T48-F318 to the top of the Torus.

Includes welds 2T48-2CPI-18-POT-2, 3, and 4.

By system, the above exemptions were applied as follows:

1. 2C11 Control Rod Drive (CRD) System (See Boundary Diagram HB-26006 Sheets 1 and

2) - The Class 2 portion of this system is less than 4" in diameter and exempt from examination, except for the 8" Scram Discharg e Header. In the March 5, 1982 response to NUREG-0803, it was stated in part, "The headers are not exempted because of size, but are not presently included in Georgia Power's ISI weld examination program because they are rarely pressurized during normal operation, a nd then only to a pressure far below design pressure". This position ha s been continued through the 1 st , 2 nd , 3 rd and 4 th Intervals. However, these welds do receive augmented exams per the March 5, 1982 letter, thus the 8" scram discharge header receives the same examinations as required by Code. The only difference is that the exams are augmented exams, not Code exams.

2. 2C41- Standby Liquid Control (SLC) System (See Boundary Diagram HB-26009). All components are exempt from examination because all piping is 4" NPS and less in diameter.

3. 2C71 Reactor Protection System (See Boundary Diagram HB-28001). All components are exempt from examination because all piping is 4" NPS and less in diameter.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 4 of 33 Rev. 1

4. 2E11 Residual Heat Removal (RHR) System (See Boundary Diagrams HB-26014&15) -This system has ECC, CHR, and reactor residual heat removal functions; therefore, the pressure/temperature exemption cannot be applied. Exemptions are open-ended piping and the 4" NPS and less size exemption.

5. 2E21 Core Spray (CS) System (See Boundary Diagrams HB-26018&19). This system has ECC and CHR functions; therefore, the pressure/temperature exemption cannot be applied.

There is not any open-ended pi ping; therefore, the only exemption is the 4" NPS and less size exemption.

6. 2E41 High Pressure Coolant Injection (HPCI) System (See Boundary Diagrams HB-26020&21 and HB-26046). This system has an ECC function; therefore, the pressure/temperature exemption cannot be appl ied. It is SNC's pos ition that the steam exhaust lines contain water; therefore, the open-ended exemption cannot be applied. The only exemption applied is the 4" NPS and less size exemption.

7. 2E51 Reactor Core Isolation Cooling (See Boundary Diagrams HB-26023&24 and HB-26046). Only a small portion of RCIC is classified as Class 2 per Boundary Diagram HB-26023, with the remainder designated as Class S (see augmented section). Per Section 5.5.6.1 of the UFSAR, the function of this system is to ensure that ad equate core cooling takes place to prevent the reactor fuel from overheating in the event that reactor isolation is accompanied by loss of flow from the reactor feedwater system. This is not an RHR, ECC, or CHR function; therefore, all piping 4" and less in diameter is considered exempt from examination per IWC-1222(a) and all piping operating at a temperature equal to or less than 200 0 F is considered exempt per IWC-1220(c). Non-exempt Class 2 RCIC piping is:

Welds 2E51-2RCIC-6-TS-3 through 10 on the 6" portion of piping from the Torus connection out to valve 2E51-F 031. (Shown on Figure B-86). This piping is potentially subject to temperatures greater than 200 0F during accident conditions; therefore, the pressure and temperature exemption cannot be applied. Since the size exemption and open-ended exemption cannot be applied, these 9 welds are not exempt.

However, this is Class HLB, Schedule 40 piping which is less than 0.375" thick and not subject to examination , but is part of the total number of non-exempt welds.

The 6" portion of piping (welds 2E51-2 RCIC-6-D-1&2) that connects the RCIC discharge to Class 2 Feedwater. (Shown on Figure B-66B). This system functions with the pressure above 275 psig and at a temperature greater than 200 0F; therefore, the pressure and temperature exemption can not be applied. Since the size exemption and open-ended exemption cannot be applied, these two welds are not exempt.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 5 of 33 Rev. 1 The 10"portion of piping (2E51-2RCIC-10-TD-16A through 21) from the Torus connection out to valve 2E51-F 040. (Shown on Figure B-82). This piping is subject to temperatures greater than 200 0F; therefore, the pressure and temperature exemption cannot be applied. The open-ended exemption was not used because while the welds in question may not be under water the environmen t in the pipe is water or vapor. Since the size exemption and open-ended exemption cannot be applied, these welds are not exempt. However, this is Class HLB, Schedule 40 piping which is 0.365" thick and not subject to examination, but is part of the total number of non-exempt welds.

For the above listed Class 2 piping, only the 6" piping is subject to examination. The other welds are not subject to examination (but are lis ted in the total C-F-2 weld count) due to the wall-thickness; however, the associated component supports and welded attachments are subject to examination.

The remainder of the RCIC piping is designated as Class S (see Class 2 augmented).

8. 2G31 Reactor Water Cleanup (RWCU) System (See Boundary Diagram HB-26036). All components are exempt from examination because all piping is 4" NPS and less in diameter.

9. 2G41 Fuel Pool Cooling System (See Boundary Diagram HB-26039). There are no Class 2 components in the 2G41 system. The Class 2 inter-tie to RHR is shown on RHR drawing HB-26014.

10. 2G51 Torus Drain (See Boundary Diagram HB-26042) - This system provides no safety function except for a containment function. Ho wever, since it is connected to the Torus it may see an elevated temperature during accident conditions. The open-ended exemption cannot be used since the piping contains water and the piping is 8" so the size exemption cannot be used.

11. 2N11/2N37 Main Steam (MS) System (See Boundary Diagrams HB-21012 and the Class 2 portions of the Nuclear Boiler System Boundary Diagrams HB-26000, HB-26001, and HB-26189). This system functions with the pressure above 275 psig and at a temperature greater than 200 0 F; therefore, the pressure/temperature exemption cannot be applied. The only exemption applied to this piping is the 4" NPS and less size exemption.

12. 2N21 Feedwater System between the second and third feed water check valve (See Nuclear Boiler System boundary Diagram HB-26000). This system functions with the pressure

above 275 psig and at a temperature greater than 200 0F; therefore, the pressure/temperature exemption cannot be applied. The only exempti on applied to this piping is the 4" NPS and less size exemption.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 6 of 33 Rev. 1

13. 2N22 Main Steam Drain Lines - Per page 12 of the SER [regarding MSIV Leakage Control System (LCS)], the licensee has committed to include the alternate LCS in the ASME Section XI inservice inspection program. The piping (drain line piping downstream of 2B21-F021 to the condenser) will be treated as ASME Code Section III, Class 2. Any repairs or replacement of this piping should also be performed in accordance with Section XI requirements. All of this piping is exempt per the 4" NPS and less size exemption.

14. 2P42 Reactor Building Closed Cooling Water (RBCCW) System (See Boundary Diagram HB-26055). Per Boundary Diagram HB-26055 the piping from the outboard isolation valve, the piping through the penetration, and the piping inside containment are designated as Class 2 because of the containm ent function. This piping provides cooling water to the reactor recirculation pump motor bearings inside containment. Per Section 9.2.2 of the UFSAR, the RBCCW system is not required to be operable following a LOCA.

This is not an RHR, ECC, or CHR function; therefore, the size exemption and pressure/temperature exemption may be us ed where applicable. Since the piping experiences low pressure and low temperature, both the size exemption and the pressure/temperature exemption may by applied. Therefore, all Class 2 RBCCW components are exempt from examination.

15. 2T48 Containment Purge and Inerting (See Boundary Diagram HB-26084 and HB-26083). This system allows the containment pre ssure to be controlled in case of a pipe rupture, allows any hydrogen buildup to be vented, and allows heat to be removed from the containment. Since heat may be removed from the containment by this system, it is considered as having a CHR function and the pressure and temperature exemption was not used. Much of this piping could be exem pted using the open-ended exemption; however, only the size exemption was used during the 3 rd Interval. The use of the open-ended exemption during the 4 th Interval should be evaluated.

16. 2T45 Primary Containment Valve a nd Equipment Drainage System (See Boundary Diagram HB-26077). All components are exempt from examination because all piping is 4" NPS and less in diameter.

17. 2T49 Post LOCA Hydrogen Recombiner System (See Boundary Diagram HB-26068) - This purpose of this was to maintain hydrogen levels below combustion levels during Post-LOCA conditions. Credit is not taken for this function; therefore, only the piping functioning as a Containment Isolation function will be considered. However, all of this piping may be exempted using the open-ended exemption.

18. Containment Isolation Piping. This piping is designated as Class 2 only because it penetrates containment and may have both the 4" exemption and the pressure/temperature exemption applied. The applicable containm ent penetrations, thei r function, the Boundary Diagram, and the size are listed below in Table 1:

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 7 of 33 Rev. 1 TABLE 1 Penetration Description Drawing Dia Evaluation X-3 H 2 O 2 Sample HB-26048 1" Size Exempt X-18 Radwaste HB-26026 3" Size Exempt X-19 Radwaste HB-26026 4" Size Exempt X-21 Service Air HB-26058 2" Size Exempt X-22 Drywell Pneumatic HB-26023 <4" Size Exempt X-23 RBCCW HB-26055 6" PT Exempt X-24 RBCCW HB-26055 6" PT Exempt X-28 H 2 O 2 Sample HB-26048 1" Size Exempt X-32A,C Drywell Pressure HB-26014 1" Size Exempt X-34C, D ILRT HB-26057 1" Size Exempt X-35A-E Neutron MonitoringHB-26993 <4" Size Exempt X-44 Nitrogen Inerting HB-26083 2" Size Exempt X-45D, 52F PASS HB-26384 2" Size Exempt X-46 Demin. Water HB-26047 2" Size Exempt X-47, 48 Chilled Water HB-26081 2", 3", 4", 6" 2", 3", 4"are size exempt. 6"

is PT Exempt. X-51C, D Drywell Pneumatic HB-26066 HB-28023 Size Exempt X-54A,C Drywell Pressure HB-26015 1" Size Exempt X-55 Radwaste HB-26026 1-1/2" Size Exempt X-60A H 2 O 2 Sample HB-26048 1" Size Exempt X-60B, 62 Fission Prod. Mon. HB-26016 1" Size Exempt X-63 Drywell Pneumatic HB-26066 1" Size Exempt X-64 H 2 O 2 Sample HB-26048 1" Size Exempt X-69 Differential Press. HB-26079 4" Size Exempt X-81 Nitrogen Inerting HB-26083 2" Size Exempt X-206A,C,F,H Instrument Lines HB-26084 1" Size Exempt X-209A-D Instrument Lines HB-26084 1" Size Exempt X-216A,C,D H 2 O 2 Sample HB-26048 1" Size Exempt X-217A,B H 2 O 2 Sample HB-26048 1" Size Exempt X-217C Fission Prod. Mon. HB-26016 1" Size Exempt X-230, 231 Nitrogen Inerting HB-26083 2" Size Exempt X-233 Differential Press. HB-26079 8" Open-Ended Exemption X-234A Torus Drainage HB-26042 3" Size Exempt

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 8 of 33 Rev. 1 DEVIATIONS TO CLASS 2 ISI CODE REQUIREMENTS IWC-2500 provides the examination requirements for Class 2 components. These Code requirements may be deviated from by:

The use of NRC approved alternatives to Code requirements per 10 CFR 50.55a(a)(3). The use of NRC approved Relief Requests per 10 CFR 50.55a(g)(6) when an examination requirement by the Code is determined to be impractical. The use of Code Cases approved for use by the NRC through publication in Regulatory Guide 1.147.

Significant deviations from IWC-2500 Code requirements at HNP-1 are:

(Note: See Volume 1 for listing of Relief Requests, Alternatives , and NRC Safety Evaluations).

Code Case N-663 Code Case N- 663 provides that "... in lieu of the surface examination requirements for piping welds of Examination Category C-F-1 and C-F-2 ,surface examinations may be limited to areas identified by the Owner as susceptible to outside surface attack." The susceptibility criteria are listed in Table 1 of Code Case N- 663 for two types of degradation mechanisms. No Class 2 welds have been identified as being susceptible to outside surface attack. The basis is discussed below:

External (O. D.) Chloride Stress Corrosi on Cracking of Austenitic Stainless Steel

NA - There is not any Austenitic Stainless Steel in Class 2 piping.

Other Outside Surface Initiated Mechanisms

Per Code Case N-663, items that are susceptible to an outside attack should be identified by a plant-specific service history re view. This review should incl ude plant-specific processes and programs that minimize chlorides and other contaminants.

For carbon steel piping, chlorides are not a issue.

During 30 years of In service Inspection of Class 2 components, outside attack of Cla ss 2 components has not been identified.

Plant-specific processes and programs that minimize chlorides and other contaminants are:

The SNC Chemical Product Control Program pr ovides procedure guidance for control of contaminants from chemical products to be used on site. Reference Hatch procedure 60 AC HPX-008-0, E. I. Hatch Chemical Control.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 9 of 33 Rev. 1 Category C-A Pressure Retainin g Welds in Pressure Vessels 1 st Interval Not Evaluated

2 nd Interval The examinations are shown in Interval 3 table for information purposes only.

3 rd Interval There are two Class 2 vessels at Hatch - the two RHR Heat Exchange rs. Per Table IWC-2500-1, Category C-A of the 1989 Code only the welds on one of the two heat exchangers need to be volumetrically examined. (Alternately the number of welds on one heat exchanger may be distributed over two heat exchangers). Welds to be volumetrically examined on the one heat exchanger include:

Circumferential shell welds at a structural discontinuity (Item C1.10). Head-to-shell we lds (Item C1.20). Tubesheet-to-shell welds (Item C1.30). NA to Hatch because the tubesheet is flanged in.

The HNP-2 Category C-A examinations are shown below in Table 2:

TABLE 2 - CATEGORY C-A PRESSURE VESSEL WELDS Item No. Component ISI Fig I2/P1 I2/P2 I2/P3 I3/P1 I3/P2 I3/P3 Comments C1.20 2E11\2HX-A-1 Shell Head To Upper Shell Ring B-1 1992 2001 Limited coverage due to brackets.

See RR-5. C1.10 2E11\2HX-A-2 Upper Shell Ring To Lower Shell Ring B-1 1995 2005 C1.10 2E11\2HX-A-3 Lower Shell Ring To Flange B-1 9/86 1998 C1.20 2E11\2HX-B-1 Shell Head To Upper Shell Rin g B-1 Examination required only on RHR "A"C1.10 2E11\2HX-B-2 Upper Shell Ring To Lower Shell Ring B-1 Examination required only on RHR "A" C1.10 2E11\2HX-B-3 Lower Shell Ring To Flange B-1 Examination required only on RHR "A" HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 10 of 33 Rev. 1 4th Interval

Examinations performed during the 3rd Interval will be repeated during the 4 th Interval.

The HNP-2 Category C-A examinations are shown below in Table 3:

TABLE 3 - CATEGORY C-A PRESSURE VESSEL WELDS Item No. Component ISI Fig I3/P1 I3/P2 I3/P3 I4/P1 I4/P2 I4/P3 Comments C1.20 2E11\2HX-A-1 Shell Head To Upper Shell Ring B-1 2001 2R21 Limited coverage due to brackets. C1.10 2E11\2HX-A-2 Upper Shell Ring To Lower Shell Ring B-1 2005 2R23 C1.10 2E11\2HX-A-3 Lower Shell Ring To Flange B-1 1998 2R20 C1.20 2E11\2HX-B-1 Shell Head To Upper Shell Rin g B-1 Examination required only on RHR "A"C1.10 2E11\2HX-B-2 Upper Shell Ring To Lower Shell Ring B-1 Examination required only on RHR "A" C1.10 2E11\2HX-B-3 Lower Shell Ring To Flange B-1 Examination required only on RHR "A" Number of 4 th Interval Examinations and Cumulative Percentage 1 (33%)2 (66%)3 (100)%

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 11 of 33 Rev. 1 Category C-B Nozzle Examinations in Class 2 Pressure Vessels 1 st Interval Not Evaluated

2 nd Interval The "A" outlet nozzle weld, the "A" nozzle inner radius, and the "B" Inlet nozzle weld were examined as shown in Interval 3 Table. The "B" Inlet nozzle inner radius was not examined because of an SNC interpretation that the configuration had a rounded corner instead of an actual inner radius configuration.

3 rd Interval There are two Class 2 vessels at Hatch - the RHR Heat Exchangers. Each RHR heat exchanger has one inlet and one outlet nozzle on each heat exchanger. The nozzles do not have reinforcement plates. For nozzles without reinforcement plates Table IWC-2500-1, Category C-B of the 1989 Code requires that only the nozzl es on one of the two heat exchangers be examined. (Alternately the number of nozzles on one heat exchanger ma y be distributed over two heat exchangers). The nozzles initially selected for examination shall be re-examined over the life of the heat exchangers. Beca use of the pattern established in the 2 nd Interval the "A" outlet nozzle and the "B" inlet nozzle will be examined. Examinations include surface and volumetric examinations of the two nozzle-to-shell welds and a volumetric examination of the inner radius volume on the two nozzles.

As discussed above in the 2 nd Interval write-up, an interpretation was made that there was a rounded corner instead of an inner radius configur ation. However, a 2004 review of drawings in manual S-25700 indicates that the configuration is similar to that shown in examination Figure IWC-2500-4(b) in the 1989 Code. While not exactly the same c onfiguration, the Code figures are representative figures and it was not the intent of the Secti on XI Code to have an "exact" match of every configuration in the nuclear industry. While there is some debate as to the accuracy of the design drawing as compared to the actual configuration and there is additional debate regarding the ability to perform meaningful examinations, a somewhat more conservative approach was used for the 3 rd Interval and the examinations were performed.

However, as shown in Table 4 below, the 3 rd Interval examinations were performed significantly more than 10-years after the previous examina tions. There was no cracking, so the structural integrity of the nozzle inner ra dii was verified for both the 2 nd and 3rd Intervals. Therefore, there is not be a technical or safety issue. The basis for this determination is that since they were not cracked during 2R18, then th ey were not cracked during the 2 nd Interval.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 12 of 33 Rev. 1 TABLE 4 - CATEGORY C-B PRESSURE VESSEL NOZZLE EXAMINATIONS Item Number Component ISI Figure Number I2/P1 I2/P2 I2/P3 I3/P1 I3/P2 I3/P3 Comments C2.21 2E11\2HX-A-I Inlet Nozzle B-1A C2.22 2E11\2HX-A-I-IRS Inlet Nozzle Inner Radius B-1A C2.21 2E11\2HX-A-O Outlet Nozzle B-1A 1986 1998 C2.22 2E11\2HX-A-O-IRS Outlet Nozzle Inner Radius B-1B 1986 2R18 C2.21 2E11\2HX-B-I Inlet Nozzle B-1B 1992 2R18 C2.22 2E11\2HX-B-I-IRS Inlet Nozzle Inner Radius B-1B 2R18 C2.21 2E11\2HX-B-O Outlet Nozzle B-1B C2.22 2E11\2HX-B-O-IRS Outlet Nozzle Inner Radius B-1B HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 13 of 33 Rev. 1 4th Interval

The HNP-2 Category C-B examinations are shown below in Table 5:

TABLE 5 - CATEGORY C-B PRESSURE VESSEL NOZZLE EXAMINATIONS Item Number Component ISI Figure Number I3/P1 I3/P2 I3/P3 I4/P1 I4/P2 I4/P3 Comments C2.21 2E11\2HX-A-I Inlet Nozzle B-1A C2.22 2E11\2HX-A-I-IRS Inlet Nozzle Inner Radius B-1A C2.21 2E11\2HX-A-O Outlet Nozzle B-1A 1998 2R20 C2.22 2E11\2HX-A-O-IRS Outlet Nozzle Inner Radius B-1B 2R18 2R21 C2.21 2E11\2HX-B-I Inlet Nozzle B-1B 2R18 2R22 C2.22 2E11\2HX-B-I-IRS Inlet Nozzle Inner Radius B-1B 2R18 2R22 C2.21 2E11\2HX-B-O Outlet Nozzle B-1B C2.22 2E11\2HX-B-O-IRS Outlet Nozzle Inner Radius B-1B Number of 4 th Interval Examinations and Cumulative Percentage 1 (25%)2 (50%) 4 (100)%

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 14 of 33 Rev. 1 Category C-C Integral Attachments for Class 2 Vessels, Piping, Pumps, and Valves 1 st and 2 nd Interval Not evaluated.

3 rd Interval Table IWC-2500-1, Category C-C of the 1989 Code defines the examination requirements for Class 2 integrally welded attachments. In lieu of these requirements, HNP examines Class 2 welded attachments per the requirements of Code Case N-509, which was originally adopted for use at HNP through relief request RR-4. Re lief Request RR-4 was superseded via the endorsement of Code Case N-509 in Revisi on 12 to Regulatory Guide 1.147. Revision 13 subsequently annulled the Code Case; however, it may be used until the end of the 3 rd interval.

Revision 12 had a condition for use, in that, at least 10% of each Item No. was required to be examined (for those items not already requiring 100%). Each Class 2 Code Case N-509 Item is discussed below.

Code Case N-509, Item C3.10 - Pressure Vessels -

As shown in Table 6, the only Class 2 pressure vessels are the two RHR Heat Exchangers. With multiple vessels, Code Case N-509 allows the examination of one of the welded attachment on one of the vessels. 2E11\2HX-A-2S-4 was examined in the 1 st Period (2R14).

Table 6 - CATEGORY C-C, ITEM C3.10 PRESSURE VESSEL WELDED ATTACHMENTS Component ISI Figure I3/P1 I3/P2 I3/P3 Comments 2E11\2HX-A-2S-1 B-1 2E11\2HX-A-2S-2 B-1 2E11\2HX-A-2S-3 B-1 2E11\2HX-A-2S-4 B-1 -2R14 One welded attachment on one vessel required to be examined per Code Case N-509 2E11\2HX-A-3S-1 B-1 2E11\2HX-A-3S-2 B-1 2E11\2HX-A-3S-3 B-1 2E11\2HX-A-3S-4 B-1 2E11\2HX-B-2S-1 B-1 2E11\2HX-B-2S-2 B-1 2E11\2HX-B-2S-3 B-1 2E11\2HX-B-2S-4 B-1 2E11\2HX-B-3S-1 B-1 2E11\2HX-B-3S-2 B-1 2E11\2HX-B-3S-3 B-1 2E11\2HX-B-3S-4 B-1 HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 15 of 33 Rev. 1 Code Case N-509, Item C3.30 (Pumps) and C3.40 (Valves)

None Identified

Code Case N-509, Item C3.20 - Piping -

Per the NRC condition of us e in Revision 12 of Reg. Guide 1.147, 10% of the piping attachments must be examined.

There are 150 sets of non-exempt welded attachments in the Class 2 scope, as shown in Schedule Works. For the purpose of this discussion, a set is a group of welded attachments associated with a specific location. For instance, a hanger clamp may have four welded lugs but it is considered one set. When a set of welded attachments is selected for examination all of the welded attachments in that set should be examined.

A minimum of 15 sets of welded attachments is required; however, 17 sets of welded attachments were examined. Six sets of welded attachments were examined during the 1 st Period, six sets during the 2 nd Period, and 5 sets during the 3 rd Period. Note: A review of the Indication Notification Forms for 3 rd Period, 2 nd Interval outages 2R11 and 2R12, and 3 rd Interval outages 2R13, 2R14, 2R15, 2R16, and 2R17 did not identify any cases requiring additional examina tions of piping welded attachments (e.g., scope expansion or re-examination). Therefore, all examinations are for Code credit.

Examinations were performed as shown in the attached Hatch Unit No. 2 Code Compliance Scheduling Summary - 3 rd Interval for Item C3.20.

Additionally, examination of an integrally welded attachment is required if the associated component support member has deformati on identified during operation, refueling, maintenance, examination, inservice inspection, or testing. An example of component support deformation is broken parts, bent parts, or pulled out parts.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 16 of 33 Rev. 1 4th Interval Table IWC-2500-1, Category C-C of the 2001 Ed ition of ASME Section XI through the 2003 Addenda defines the examination requirements for Class 2 integrally welded attachments. These requirements mirror those in Code Case N-509 used during the 3rd Interval.

Item C3.10 - Pressure Vessels

- As shown in Table 7, the only Class 2 pressure vessels are the two RHR Heat Exchangers. With multiple vessels, the Code allows the examination of one of the welded attachment on one of the vessels.

2E11\2HX-A-2S-4 was examined in the 1 st Period of the 3rd Interval and will be re-examined during the 1st Period of the 4 th Interval.

TABLE 7 - CATEGORY C-C, ITEM C3.10 PRESSURE VESSEL WELDED ATTACHMENTS Component ISI Figure I4/P1 I4/P2 I4/P3 Comments 2E11\2HX-A-2S-1 B-1 2E11\2HX-A-2S-2 B-1 2E11\2HX-A-2S-3 B-1 2E11\2HX-A-2S-4 B-1 2R20 One welded attachment on one vessel required to be examined. 2E11\2HX-A-3S-1 B-1 2E11\2HX-A-3S-2 B-1 2E11\2HX-A-3S-3 B-1 2E11\2HX-A-3S-4 B-1 2E11\2HX-B-2S-1 B-1 2E11\2HX-B-2S-2 B-1 2E11\2HX-B-2S-3 B-1 2E11\2HX-B-2S-4 B-1 2E11\2HX-B-3S-1 B-1 2E11\2HX-B-3S-2 B-1 2E11\2HX-B-3S-3 B-1 2E11\2HX-B-3S-4 B-1 Item C3.30 (Pumps) and C3.40 (Valves)

None Identified

Item C3.20 - Piping - There are 150 sets of non-exempt welded attachments in the Class 2 scope, as shown in Schedule Works. For the pur pose of this discussion, a set is a group of welded attachments associated with a specific location. For instance, a hanger clamp may have four welded lugs but it is considered one set. When a set of welded attachments is selected for examination all of the welded attachments in that set should be examined.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 17 of 33 Rev. 1 A minimum of 15 sets of welded attachments is required and 16 are scheduled. Five sets of welded attachments (31%) will be examined during the 1st Period, 6 sets during the 2nd Period (cumulative percentage of 69%), and 5 sets during the 3rd Period (Cumulative percentage of 100%).

Examinations were performed as shown in the attached Hatch Unit No. 2 Code Compliance Scheduling Summary - 3 rd Interval for Item C3.20.

Additionally, examination of an integrally welded attachment is required if the associated component support member has deformati on identified during operation, refueling, maintenance, examination, inservice inspection, or testing. An example of component support deformation is broken parts, bent parts, or pulled out parts.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 18 of 33 Rev. 1 Category C-F-1 Pressure Retaining Welds in Austenitic Stainless Steel None Identified

Category C-F-2 Pressure Retaining Welds in Carbon or Low Alloy Steel 1st and 2 nd Intervals - Not Evaluated 3 rd Interval - See 3 rd Interval ISI Plan 4 th Interval Table IWC-2500-1, Category C-F-2 of the 2001 Ed ition of Section XI with Addenda through 2003 defines the examination requirements for these piping welds.

1. The Code requires that welds selected for examination shall in clude 7.5% , but not less than 28 circumferential welds not exempted by IWC-1220. Long-seam welds are not required for examination by the Code.

2. The Code indicates in Table IWC-2500-1, Category C-F-2, Footnote 2 that some welds that are not exempted by IWC-1220 are not required to be examined, because they are less than 3/8" (0.375") thick, but they are required to be included in the total we ld count to which the 7.5% sample will be applied. Per the Code Compliance Scheduling Summary for C-F-2 welds there are 1170 welds in th e population, requiring 88 exam inations. For Category C-F-2, not all of the roundup will be used because the welds were broken out by system in order to facilitate the implementation of (the below listed) proration requireme nts. Allowing all of the roundup would require an excess number of examinations. Additionally, there is not a Code requirement to meet the 7.5% percentage requirements for each Code Item, but only for the total category C-F-2 welds. Using the below listed proration requirements the Code requirements will be met. (Note: 94 welds were selected.)

3. Table IWC-2500-1, Category C-F-2, Footnote 2 of the Code requires that the exams be distributed (prorated) among Class 2 systems, to the degree practicable using the following criteria:

the number of non-exempt welds in each system as compared to the total number of non-exempt welds. the number of non-exempt welds for each line size (e.g., 10", 12" and 16") to the degree practicable.

4. Per Table IWC-2420-B, a review of the Indication Notification Forms for 3rd Period, 2nd Interval outages 2R11 and 2R12, and 3rd In terval outages 2R13, 2R14, 2R15, 2R16, and 2R17 did not identify any cases requiring additional examina tions of piping welds (e.g., scope expansion or re-examination). Therefore, all examin ations are for Code credit

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 19 of 33 Rev. 1 RHR (2E11) - RHR has a total of 531 C-F-2 welds versus a total of 1170 total welds; therefore about 40 of the 88 welds need to be selected in RHR (more may be selected if desired). These 40 welds are prorat ed through the line sizes as follows.

TABLE 8 RHR SYSTEM C-F-2 WELDS RHR Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 1E11 6" 4 (1%) 0 8" 6 (1%) 0 16" 122 (31%) 14 20" 122 (31%) 13 24" 145 (36%) 15 399 42 CS (2E21) - CS has a total of 199 C-F-2 welds vers us a total of 1170 welds; therefore about 15 of the 88 welds need to be selected in CS (more may be selected if desired). These 15 welds are prorated through the line sizes as follows.

TABLE 9 CORE SPRAY SYSTEM C-F-2 WELDS CS Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 12" 75 (54%) 8 14" 18 (13%) 2 20" 46 (33%) 5 139 15 HPCI (2E41)- HPCI has a total of 194 C-F-2 welds ve rsus a total of 1170 welds; therefore about 15 of the 88 welds need to be selected in HPCI (more may be selected if desired).

These 15 welds are prorated through the line sizes as follows.

TABLE 10 HPCI SYSTEM C-F-2 WELDS HPCI Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 6" 2 (1%) 1 10" 51 (30%) 4 12" 7 (4%) 1 14" 52 (30%) 4 16" 31 (18%) 3 18" 4 (2%) 0 20" 24 (14%) 3 24" 1 (<1%) 0 172 16 HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 20 of 33 Rev. 1 RCIC (2E51) - RCIC has a total of 17 C-F-2 welds ve rsus a total of 1170 welds; therefore about 1 of the 88 welds need to be selected in RCIC.

TABLE 11 RCIC SYSTEM C-F-2 WELDS RCIC Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 6" 2 1 Torus Drainage (2G51) - TDP has a total of 10 C-F-2 welds versus a total of 1170 welds; therefore one of the 88 welds c ould be selected in TDP. However, all welds are less than

.375" thick, so none were selected.

TABLE 12 TORUS DRAINAGE SYSTEM C-F-2 WELDS TDP Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 8" 0 0 0 0 Main Steam (2N11) - MS has a total of 165 C-F-2 weld s versus a total of 1170 welds; therefore about 12 of the 88 welds need to be selected in MS (more may be selected if desired). These 12 welds are prorat ed through the line sizes as follows.

TABLE 13 MAIN STEAM SYSTEM C-F-2 WELDS MS Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 6" 3 (2%) 0 8" 12 (7%) 1 10" 4 (2%) 0 14" 6 (4%) 1 16" 58 (35%) 4 24" 82 (50%) 6 165 12 Feedwater (2N21): There are six 18" non-exempt welds versus a total of 1170 welds; therefore, one weld will be examined.

TABLE 14 FEEDWATER SYSTEM C-F-2 WELDS Aux Steam Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 18" 6 (100%) 1 6 1 HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 21 of 33 Rev. 1 Purge and Inerting (T48) - This system has a total of 51 C-F-2 welds versus a total of 1170 welds; therefore about 4 of the 88 welds need to be selected in T48 (more may be selected if desired). These 4 welds are prorated through the line sizes as follows.

TABLE 15 PURGE AND INERTING SYSTEM C-F-2 WELDS Purge Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 18" 18 (75%) 3 20" 6 (25%) 2 1 extra weld selected 24 5

5. Footnote 2 indicates that this prorated number of weld examinations determined for each system as shown in the above tables should then be distributed among terminal ends and structural discontinuities pror ated, to the degree practicable, on the number of non-exempt terminal ends and structural discontinuities within a system. Stru ctural discontinuities include pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (such as elbows, tees, reducers, flanges, etc.), and pipe branch connections and fittings. Terminal ends would be those structur al discontinuities where a pipi ng connects to structures, components, or pipe anchors

An evaluation of the Footnote 2 requirements is performed below for each system.

2E11 - RHR: Per Schedule Works there are there are 531 non-exempt welds. Removing the pipe-to-pipe welds and the welds less than 0.375" thick, there are 366 welds subject to examination. Of these 366 welds, the follo wing 18 welds (4.9% of the 366 welds) are considered terminal end welds and the remainder are structural discontinuities:

Piping Welds Connecting to the Torus

2E11-2RHR-24A-TS-A-2 (Note: weld A-1 is in the IWE scope) 2E11-2RHR-24A-TS-C-2 (Note:

weld C-1 is in the IWE scope) 2E11-2RHR-24B-TS-B-2 (Note:

weld B-1 is in the IWE scope) 2E11-2RHR-24B-TS-D-2 (Note: weld D-1 is in the IWE scope) 2E11-2RHR-16A-SH-15 (Note: weld SH-16 is in the IWE scope) 2E11-2RHR-16B-SH-19 (Note: weld SH-20 is in the IWE scope)

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 22 of 33 Rev. 1 Piping Welds Connecting to Pump Nozzles

2E11-2RHR-16A-PD-A-1

2E11-2RHR-16A-PD-C-1

2E11-2RHR-16B-PD-B-1

2E11-2RHR-16B-PD-D-1

2E11-2RHR-24A-TS-A-18

2E11-2RHR-24A-TS-C-19

2E11-2RHR-24B-TS-B-18

2E11-2RHR-24B-TS-D-19

Piping Welds Connecting to RHR Heat Exchanger Nozzles

2E11-2RHR-20A-HXI-1 2E11-2RHR-20A-HXO-1

2E11-2RHR-20B-HXI-1 2E11-2RHR-20B-HXO-1

Since 4.9% of the RHR population are terminal ends, two terminal ends (or 4.8% of the 42 welds defined in Table 8) are scheduled for examination. These are 2E11-2RHR-24A-TS-A-2 and 2E11-2RHR-24B-TS-B-18. The remaining welds scheduled for examination are structural discontinuities.

2E21 - Core Spray - Per Schedule Works there are 199 non-exempt welds. Removing the pipe-to-pipe welds and the welds less than 0.375" thick, there are 130 welds subject to examination. Of these 130 welds, the follo wing 4 welds (3.1% of the 130 welds) are considered terminal end welds and the remainder are structural discontinuities:

Piping Welds Connecting to the Torus

2E21-2CS-20A-TS-2 (Note: weld TS-1 is in the IWE scope) 2E21-2CS-20B-TS-2 (Note: weld TS-1 is in the IWE scope)

Piping Welds Connecting to Pump Nozzles

2E21-2CS-12A-1 2E21-2CS-20A-TS-22 2E21-2CS-12B-1 2E21-2CS-20B-TS-21

Since 3.1% of the Core Spray population are terminal ends, one terminal end (or 6.7% of the 15 welds defined in Table 9) is scheduled for examination. This weld is 2E21-2CS-20B-TS-2. The remaining welds scheduled for examination are structural discontinuities.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 23 of 33 Rev. 1 2E41 - HPCI: Per Schedule Works there are 194 non-exempt welds. (This includes an estimate of the welds on the 16" suction line from the Conde nsate Storage Tank to the Reactor Building wall. Per drawings H-21084 and H-21110 there is about 65' of piping that is greater than or equal to 0.375 thick and there is about 10 fitting welds. Assuming 5 pipe-to-pipe welds in the run of pipe and adding this number to the 10 fitting welds would yield a total of 15 welds. This is piping is HAC, Schedule 10S piping not subject to examinations, but the welds must be ac counted for in the total). Removing the pipe-to-pipe welds and the welds less than 0.375" thick, there are 157 welds subject to examination. Of these 157 welds, the following 7 welds (4.5% of the 157 welds) are considered terminal end welds and the remainder are structural discontinuities:

Piping Weld Connecting to the CST

One unnumbered weld.

Piping Welds Connecting to the Torus

2E41-2HPCI-16-TS-2 (Note: weld TS-1 is in the IWE scope) 2E41-2HPCI-24-TD-1 (Note: weld TD-2 is in the IWE scope)

Piping Welds Connecting to Pump Nozzles

2E41-2HPCI-10-R-1 (discharge) 2E41-2HPCI-16-TS-25 (suction) 2E41-2HPCI-12-PC-1 (booster pump connection) 2E41-2HPCI-12-PC-5 (booster pump connection)

Since 4.5% of the HPCI population are terminal ends, one terminal end (or 6.3% of the 16 welds defined in Table 10) is scheduled for examination. This is weld 2E41-2HPCI-16TS-2.

Weld 2E41-2HPCI-12-PC-5 which is both a termin al end and a structur al discontinuity is also scheduled for examination. The remaining welds scheduled for examination are structural discontinuities.

2E51 - RCIC. Per Schedule Works there are 17 non-exem pt welds. Removing the pipe-to-pipe welds and the welds less than 0.375" thick there are 2 welds subject to examination. One is scheduled for examination.

2G51 - Torus Cleanup. Per Schedule Works there are 7 non-exempt welds. Removing the welds less than 0.375" thick, leaves zero welds subject to examination.

2N11 - Main Steam: Per Schedule Works there are 165 non-exempt welds. Removing the pipe-to-pipe welds there are 142 welds subject to examination (there ar e no thin-wall welds).

Of these 142 welds, the 4 welds to the Main Stop and Control valves are considered as terminal ends (about 2.8% of the 142 welds) sin ce the Class 2 piping run ends at the valves. The remaining 138 welds are considered as structural di scontinuities.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 24 of 33 Rev. 1 Since 2% of the population are terminal ends, one terminal end (or 5% of the 12 welds defined in Table 13) is scheduled for examination. The remaining welds scheduled for examination are structural discontinuities.

2N21 - Feedwater:

Per Schedule Works there are six 18" non-exempt welds, of which, zero are pipe to pipe. Of these 6 non-exempt welds, all 6 are structural disc ontinuities (not pipe-to-pipe), with none considered as terminal ends.

One structural discontinuity is scheduled for examination (See Table 14).

2T48 - Purge and Inerting. Per Schedule Works there are 51 non-exempt welds. Removing the pipe-to-pipe welds and the weld s less than 0.375" thick, there are 22 welds subject to examination. Of these 22 welds, th e following 2 welds (9.1% of the 22 welds ) are considered terminal end welds:

Piping Welds Dead-ending at the Vacuum Breakers

2T48-2CPI-20A-VB-1

2T48-2CPI-20B-VB-1

Since 9.1% of the Purge and Inerting population are terminal ends, one terminal end (or 50%

of the 5 welds defined in Table 15) is scheduled for examination. This is weld 2T48-20A-VB-1. The remaining welds scheduled for examination are structural discontinuities.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 25 of 33 Rev. 1 Category C-G Pressure Retaining Welds in Pumps and Valves 1 st and 2 nd Interval Not Evaluated 3 rd Interval - See 3 rd Interval ISI Plan 4th Interval (No welds have been identifie d in valve casings at Hatch)

Table IWC-2500-1, Category C-G of the 2001 Edition of Section XI with Addenda through 2003 defines the examination requirements for these welds.

For pump welds, the Code requires that in the case of multiple pumps of similar design, function, and service in a system, only the pressure retaining welds on one pump needs to be examine

d. As shown in Table 16 for Interval 4, Hatch has four Class 2 RHR pumps and two Class 2 Co re Spray pumps that have pressure-retaining welds. The welds in RHR Pump A and Core Spray Pump A are scheduled for examination during the 4th Interval as shown in Schedule Works.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 26 of 33 Rev. 1 TABLE 16 4 th INTERVAL CATEGORY C-G PUMP WELD EXAMINATIONS Component Fig I4/P1 I4/P2 I4/P3 Notes 2E11-2RHR-PLP-A-1 thru 6 2E11-2RHR-PLP-B-1 thru 6 2E11-2RHR-PLP-C-1 thru 6 2E11-2RHR-PLP-D-1 thru 6 B-2 These internal welds are not considered Category C-G pump welds. 2E11-2RHR-PMI-A B-2 X RHR Pump A - For multiple pumps only the pressure retaining welds on one pump needs to be examined. 2E11-2RHR-POP-A-1 B-2 X 2E11-2RHR-POP-A-1BC/

B-2 X 2E11-2RHR-POP-A-2 B-2 X 2E11-2RHR-PMI-B B-2 RHR Pump B 2E11-2RHR-POP-B-1 B-2 2E11-2RHR-POP-B-1BC/

B-2 2E11-2RHR-POP-B-2 B-2 2E11-2RHR-PMI-C B-2 RHR Pump C 2E11-2RHR-POP-C-1 B-2 2E11-2RHR-POP-C-1BC/

B-2 2E11-2RHR-POP-C-2 B-2 2E11-2RHR-PMI-D B-2 RHR Pump D 2E11-2RHR-POP-D-1 B-2 2E11-2RHR-POP-D-1BC/

B-2 2E11-2RHR-POP-D-2 B-2 2E21-2CS-PLP-A-1 thru 6 2E21-2CS-PLP-B-1 thru 6 B-2A These internal welds are not considered Category C-G pump welds. 2E21-2CS-PMI-A B-2A X Core Spray Pump A - For multiple pumps only the pressure retaining welds on one pump needs to be examined 2E21-2CS-POP-A-1 B-2A X 2E21-2CS-POP-A-1BC/

B-2A X 2E21-2CS-POP-A-2 B-2A X 2E21-2CS-PMI-B B-2A Core Spray Pump B 2E21-2CS-POP-B-1 B-2A 2E21-2CS-POP-B-1BC/

B-2A 2E21-2CS-POP-B-2 B-2A HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 27 of 33 Rev. 1 AUGMENTED EXAMINATIONS

The NRC's safety evaluation dated 6/16/97 of the 3rd Interval Program listed several augmented programs that will be maintained during the 4 th Interval.

NUREG-0803

The NRC's safety evaluation dated 6/16/97 of the 3 rd Interval Program indicated, that in addition to the Code required examinations, the examination of the Scram Discharge Volume (SDV) piping in accordance with NUREG-0803 would be examined. NUREG-0803 contends that since the SDV was designed and fabricated in accordance with Class 2 piping that it should be subjected to the ISI requirements for Cla ss 2 piping. By letter dated March 5, 1982 GPC committed to the following, "We will include weld examination of the SD (scram discharge) headers in the ISI program -.."

The 2 nd Interval update was performed effective 12

/31/85 and these welds were included as required. As permitted in 10CFR50.55a, examination locations were selected by the 1974 Code with addenda through Summer 1975 and the examinations were performed per the 1980 Edition

of Section XI through Winter 1981. As shown on ISI Figures B-84 and B-85 there are thirty-three (EBB, 0.5" thick, schedul e 80 carbon steel), welds.

The 1974 Code required examination of 100% of we lds that circulate reactor coolant to be examined over the 40-year life. For those systems not circulating reactor coolant the examinations could be reduced to 50% of the welds. These welds are outside the Reactor

Coolant Pressure Boundary a nd per NEDO-24342, "GE Evaluation in Response to NRC Request Regarding BWR Scram System Pipe Breaks" they are pressurized less than 1% of the time. Therefore, these welds were designated as not circulating Reactor Coolant. Additionally, because there are two similar CRD headers only the equivalent of 50% of one the headers needed to be examined during the 40-years. Since the largest header has 18 welds, 50% or nine welds have to be examined during the 40-year life or three welds per 10-year in terval. The 1980 Code required a surface examination technique for 0.5" thick piping.

For the 3 rd Interval, a 7.5% sample (3 welds) were volumetrically examined. The 1989 Code requirement to perform both a volumetric and surface examination was not followed for this augmented requirement, since RR-40 was issued to eliminate piping surface examinations. Welds and examinations are shown in Table 17. (Note: Two welds had a surface examination during the 3 rd Interval, but were not counted toward this requirement

). Code credit (i.e., C-F-2) was not taken for these examinations.

For the 4 th Interval, a 7.5% sample (volumetric) is required. Welds and examinations are shown below in Table 17. This piping is desi gnated as "Class 2S" in Schedule Works.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 28 of 33 Rev. 1 AUGMENTED EXAMINATIONS TABLE 17 AUGMENTED CRD WELD EXAMINATIONS Component I3/P1 I3/P2 I3/P3 I4/P1 14/P2 I4/P3 2C11-2CRD-8N-SDV-1 2C11-2CRD-8N-SDV-2 2C11-2CRD-8N-SDV-3 2C11-2CRD-8N-SDV-4 2C11-2CRD-8N-SDV-5 2R17 (Surf) 2C11-2CRD-8N-SDV-6 2C11-2CRD-8N-SDV-7 2C11-2CRD-8N-SDV-8 2C11-2CRD-8N-SDV-9 2C11-2CRD-8N-SDV-10 2C11-2CRD-8N-SDV-11 2C11-2CRD-8N-SDV-12 2C11-2CRD-8N-SDV-13 2C11-2CRD-8N-SDV-14 2C11-2CRD-8N-SDV-15 2C11-2CRD-8S-SDV-1 2R18 X 2C11-2CRD-8S-SDV-2 2C11-2CRD-8S-SDV-3 2C11-2CRD-8S-SDV-4 2R15 (Surf) 2C11-2CRD-8S-SDV-5 2C11-2CRD-8S-SDV-6 2C11-2CRD-8S-SDV-7 2C11-2CRD-8S-SDV-8 2C11-2CRD-8S-SDV-9 2C11-2CRD-8S-SDV-10 2C11-2CRD-8S-SDV-11 2C11-2CRD-8S-SDV-12 2R18 X 2C11-2CRD-8S-SDV-13 2R18 X 2C11-2CRD-8S-SDV-14 2C11-2CRD-8S-SDV-15 2C11-2CRD-8S-SDV-16 2C11-2CRD-8S-SDV-17 2C11-2CRD-8S-SDV-18

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 29 of 33 Rev. 1 AUGMENTED EXAMINATIONS

Thin-Wall Piping

The NRC's safety evaluation dated 6/16/97 of the 3rd Interval Program also indicated, that in addition to the 1989 Code required examinations, volumetric examination of a 7.5% sample of a portion of thin-wall, non-exemp t piping within the RHR, CS, and HPCI systems would be performed. Per Table IWC-2500-1, Category C-F-2 only carbon steel welds 3/8" (0.375") thick require examination; however, SNC agreed to volumetrically examine a 7.5% sample of the welds in this thin wall piping. The Class 2 augmented section of the 3 rd Interval ISI Program indicates that the portion of thin-wall, non exempt piping subject to examination is:

a. The thin-wall piping on the downstream side of pumps whose integrity is needed to maintain the pressure boundary for the system to perform its intended RHR, ECC, or

CHR safety function.

b. The Branch connection piping out to the first normally closed valve, or to the first valve capable of automatic closure, or to a flange when the piping downstream of the valve or flange has a non-ECCS, non-RHR, or non-CHR function.

Per pipe schedule tables, this thin wall piping is limited to Schedule 40 (o r thinner) piping 6", 8", or 10" in diameter. Table 18 shows the Class 2 welds in the thin wall scope and defines the welds that meet criteria a or criteria b. There are approximately 75 welds that meet criteria a or criteria b; therefore, at least six welds are required to be examined to meet the 7.5% requirement.

For the 4 th Interval, a 7.5% sample (volumetric) is required. As shown in Table 18 six welds were selected. Code credit (i.e., C-F-2) was not taken for these examinations.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 30 of 33 Rev. 1 TABLE 18 THIN-WALL PIPING AUGMENTED EXAMINATIONS Weld Fig I3/P1 I3/P2 I3/P3 14/P1 14/P2 14/P3 1. 2E11-2RHR-6A-DS-1 B-14 2. 2E11-2RHR-6A-DS-2 B-14 3. 2E11-2RHR-6B-DS-1 B-18 4. 2E11-2RHR-6B-DS-2 B-18 5. 2E11-2RHR-6A-TSP-1 B-17 6. 2E11-2RHR-6A-TSP-2 B-17 7. 2E11-2RHR-6A-TSP-3 B-17 8. 2E11-2RHR-6A-TSP-4 B-17 9. 2E11-2RHR-6A-TSP-5 B-17 10. 2E11-2RHR-6A-TSP-6 B-17 2R14 X 11. 2E11-2RHR-6A-TSP-7 B-17 12. 2E11-2RHR-6A-TSP-8 B-17 13. 2E11-2RHR-6A-TSP-9 B-17 14. 2E11-2RHR-6A-TSP-10 B-17 15. 2E11-2RHR-6A-TSP-11 B-17 16. 2E11-2RHR-6B-TSP-1 B-21 17. 2E11-2RHR-6B-TSP-2 B-21 18. 2E11-2RHR-6B-TSP-3 B-21 19. 2E11-2RHR-6B-TSP-4 B-21 20. 2E11-2RHR-6B-TSP-5 B-21 2R16 X 21. 2E11-2RHR-6B-TSP-6 B-21 22. 2E11-2RHR-6B-TSP-7 B-21 23. 2E11-2RHR-6B-TSP-8 B-21 24. 2E11-2RHR-6B-TSP-9 B-21 25. 2E11-2RHR-6B-TSP-10 B-21 26. 2E11-2RHR-6B-TSP-11 B-21 27. 2E11-2RHR-6B-TSP-12 B-21 28. 2E11-2RHR-8-FPD-1 B-22 29. 2E11-2RHR-8-FPD-2 B-22 2R18 X 30. 2E11-2RHR-8-FPD-3 B-22 31. 2E11-2RHR-8-FPD-4 B-22 32. 2E11-2RHR-8-FPD-5 B-22 33. 2E11-2RHR-8-FPD-6 B-22 34. 2E11-2RHR-8-FPD-7 B-22 35. 2E11-2RHR-8-FPD-8 B-22 -2R16 X 36. 2E11-2RHR-10A-SWDS-1 B-24 37. 2E11-2RHR-10A-SWDS-3 B-24 2R14 X 38. 2E11-2RHR-10A-SWDS-4 B-24 39. 2E11-2RHR-10A-SWDS-5 B-24 40. 2E11-2RHR-10A-SWDS-6 B-24 41. 2E11-2RHR-10A-SWDS-7 B-24 42. 2E11-2RHR-10A-SWDS-8 B-24 43. 2E11-2RHR-10A-SWDS-9 B-24 HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 31 of 33 Rev. 1 TABLE 18 THIN-WALL PIPING AUGMENTED EXAMINATIONS Weld Fig I3/P1 I3/P2 I3/P3 14/P1 14/P2 14/P3 44. 2E11-2RHR-10A-SWDS-B-24 45. 2E11-2RHR-10B-SWDS-1 B-25 46. 2E11-2RHR-10B-SWDS-2 B-25 47. 2E11-2RHR-10B-SWDS-3 B-25 48. 2E11-2RHR-10B-SWDS-4 B-25 49. 2E11-2RHR-10B-SWDS-5 B-25 50. 2E11-2RHR-10B-SWDS-6 B-25 51. 2E11-2RHR-10B-SWDS-7 B-25 52. 2E11-2RHR-10B-SWDS-8 B-25 53. 2E21-2CS-10A-1 B-52 54. 2E21-2CS-10A-2 B-52 55. 2E21-2CS-10A-3 B-52 56. 2E21-2CS-10A-4 B-52 57. 2E21-2CS-10A-5 B-52 58. 2E21-2CS-10A-6 B-52 2R18 X 59. 2E21-2CS-10A-7 B-52 60. 2E21-2CS-10A-8 B-52 61. 2E21-2CS-10A-9 B-52 62. 2E21-2CS-10A-10 B-52 63. 2E21-2CS-10B-1 B-54 64. 2E21-2CS-10B-2 B-54 65. 2E21-2CS-10B-3 B-54 66. 2E21-2CS-10B-4 B-54 67. 2E21-2CS-10B-5 B-54 68. 2E21-2CS-10B-6 B-54 69. 2E21-2CS-10B-7 B-54 70. 2E21-2CS-10B-8 B-54 71. 2E21-2CS-10B-9 B-54 72. 2E21-2CS-10B-10 B-54 73. 2E21-2CS-10B-11 B-54 74. 2E41-2HPCI-10-TD-1 B-69 75. 2E41-2HPCI-10-TD-2 B-69 HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 32 of 33 Rev. 1 AUGMENTED EXAMINATIONS Portions of the Reactor Core Isolation Cooli ng are designated as Cla ss S on Boundary Diagrams H-26023 and H-26024. Because this piping has importance, it will be treated using Section XI as a guideline (not as a requireme nt). As discussed for the Cla ss 2 portion of this piping, this system does not have an RHR, ECC, or CHR function; therefore, the size exemption and pressure/temperature exemption will also be used for this Class S piping. Lines within Class S are evaluated below for examination potential.

8" and 10" Steam Exhaust (Figure B-

82) - This 8" and 10"piping is not pressure temperature exempt because of the steam conditions and it is not size exempt. However, all of this HBB piping is 0.365" (.322 for the 8" weld) nominal wall thickness and therefore does not require examination of the piping welds. The five welded attachments on this line are subject to Category "CC type" examinations are shown in Table 19. They are designated as Category CC-R in Schedule Works.

6" Suction Line from valve 2E51-F031 and the Condensate Storage Tank (Figure B-86).

This piping is pressure/temperature exempt because it is highly unlikely that it would ever exceed the prescribed pressure/temperature. Therefore, examination of piping welds and integrally welded attachments are not required. (Note: Even if this piping was considered as non-exempt this HBB piping is only .280" thick and not subject to examination).

3", 4" and 6" Suction Line from valve 2E 51-F031, the Condensate Tank, and the RHR Heat Exchanger (Figure B-87). The 6" piping is pressure/temperature exempt because it is highly unlikely that the RHR function would be us ed and the piping would never exceed the prescribed pressure/temperature. The 3" and 4" piping is size exempt. Therefore, examination of piping welds and integrally welded attachments are not required. (Note: Even if the 6" piping was considered as non-exempt this 6" HBB piping is only .280" thick and not subject to examination).

4" piping from RHR (Figure B-88). Size exempt 6" Suction Line from Condensate Storag e Tank (Figure B-89). This piping is pressure/temperature exempt because it is highly unlikely that it would ever exceed the prescribed pressure/temperature. Therefore, examination of piping welds and integrally welded attachments are not requ ired. (Note: Even if this piping was considered as non-exempt this HAB piping is only .134" thick and not subject to examination).

6" Suction Line from Condensate Storag e Tank (Figure B-90). This piping is pressure/temperature exempt because it is highly unlikely that it would ever exceed the prescribed pressure/temperature. Therefore, examination of piping welds and integrally welded attachments are not requ ired. (Note: Even if this piping was considered as non-exempt this HAB piping is only .134" thick and not subject to examination).

2" and 4" piping (Figure B-91) - Size exempt.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS H2 Basis Doc - Class 2 Page 33 of 33 Rev. 1 4" Steam Supply (Figure B-95) - This piping is size exempt; therefore, examination of piping welds and integrally welded attachments in not required.

3" and 4" Steam Supply (Figure B-96) - This piping is size exempt; therefore, examination of piping welds and integrally welded attachments in not required.

4" Pump Discharge Line - This piping is size exempt; therefore, examination of piping welds and integrally welded attachments in not required.

Table 19 Class S "Non-Exempt" RCIC Integrally Welded Attachments Welded Attachment I3/P1 I3/P2 13/P3 I4/P1 I4/P2 I4/P3 2E51-2RCIC-10-TD-3PL-1 THRU 4 2E51-2RCIC-10-TD-7PS-1 2R16 X 2E51-2RCIC-10-TD-7PS-2 2E51-2RCIC-10-TD-9PS-1 THRU 4 2E51-2RCIC-10-TD-12PS-1 AND 2

Rev. 1.0 Southern Nuclear operating Company Page 1 - 1 111 012006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS C-A C1.10 4 50% 2 2 2 C-A C1.20 2 50% 1 1 1 Total: 6 3 3 3 ACTUAL ROUND COUNT PERIOD UP 1 50.00% 50% 0 0% 0% 1 33.30% 34%

ACTUAL ROUND COUNT PERIOD UP 0 50.00% 50% 1 100.00% 100%

1 66.60% 67% ACTUAL ROUND COUNT PERIOD UP 1 100.00% 100% 0 100.00% 100%

1 100% 100%

Southern Nuclear Operating Company Page I - 1 111 012006 Rev. 1 .O Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS C-B C2.21 4 50% 2 2 2 C-B C2.22 4 50% 2 2 2 Total. 8 4 4 4 ACTUAL ROUND COUNT PERIOD UP 1 50.00% 50% 0 0% 0% 1 25% 25% ACTUAL ROUND COUNT PERIOD UP 0 50.00% 50% 1 50.00% 50% 1 50% 50% ACTUAL ROUND COUNT PERIOD UP 1 100.00% 100% 1 100.00% 100% 2 100% 100%

Southern Nuclear Operating Company Page 1 - 1111012006 Rev. 1.0 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS C-C C3.10(2) 16 6.25% 1 1 1 C-C C3.20 150 10% 15 15 16 Total: 166 16 16 17 ACTUAL ROUND COUNT PERIOD UP 1 100.00%

100% 5 33.33% 34% 6 37.50% 38% ACTUAL ROUND COUNT PERIOD UP 0 100.00%

100% 6 73.33% 74% 6 75% 75% ACTUAL ROUND COUNT PERIOD UP 0 100.00%

100% 5 106.67%

107% 5 106.00%

106%

Southern Nuclear Operating Company ROUND UP 75% 54% 0% 80% 59% 0% 65% 0% 100% 100% 0% 100% 0% 0% 50% 61% Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2001 Edition with 2003 Addenda d Page 1 - 1111012006 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS C-F-2 C5.51CPI 49 7.50% 3.68 4 5 C-F-2 C5.51 CS 187 7.50% 14.03 15 15 C-F-2 C5.51 FW 5 7.50% 0.38 1 1 C-F-2 C5.51HPCI 187 7.50% 14.03 15 15 C-F-2 C5.51 MS 154 7.50%

1 1.55 12 12 C-F-2 C5.51 RCIC 16 7.50% 1.2 2 1 C-F-2 C5.51 RHR 486 7.50% 36.45 37 38 C-F-2 C5.51TDP 7 7.50% 0.53 1 0 C-F-2 C5.81CPI 2 7.50% 0.15 1 1 C-F-2 C5.81CS 12 7.50% 0.9 1 1 C-F-2 C5.81 FW 1 7.50% 0.08 1 0 C-F-2 C5.81 HPCI 8 7.50% 0.6 1 1 C-F-2 C5.81 MS 10 7.50% 0.75 1 0 C-F-2 C5.81 RCIC 2 7.50% 0.15 1 0 C-F-2 C5.81 RHR 45 7.50% 3.38 4 4 Total: 1171 88 97 94 PERIOD 3 ACTUAL ROUNI COUNT PERIOD UP 2 135.87% 125% The required percentage for each period is based on Table IWC-2412-1 and applies only to the total, not each item number. Only 88 total C-F-2 examinations are required.

94 were scheduled to allow flexibility to drop an exam during an outage if needed. PERIOD 1 ACTUAL ROUND COUNT PERIOD UP 2 54.35% 50% 6 42.77% 40% 0 0% 0% 7 49.89% 47% 2 17.32% 17% 0 0% 0% 14 38.41% 38% 0 0% 0% 1 666.67% 100% 0 0% 0% 0 0% 0% 1 166.67% 100% 0 0% 0% 0 0% 0% 0 0% 0% 33 37.50% 34% Rev. 1.0 PERIOD 2 ACTUAL COUNT PERIOD 1 81.52% 2 57.02% 0 0.00% 5 85.53% 5 60.61 % 0 0.00% 10 65.84% 0 0.00% 0 666.67% 1 111.11% 0 0.00% 0 166.67% 0 0.00% 0 0.00% 2 59.17% 26 67.00%

Revision:

1 3 HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page I - I 81312006 1 Period 1 Period 2 Period 3 C -A H2 2E11UHX-A-1 ISIIUTI B-1 IS1 C1.20 2E11 UHX-A-1 SHELL HEAD TO UPPER SHELL RING AUG 2 El 1 OWN PRE C -A H2 2E11 UHX-A-2 ISIIUTI 8-1 IS1 C1.10 2E11 UHX-A-2 RING AUG 2 El 1 OWN PRE C-A H2 2E11 UHX-A-3 ISllUTl B-1 IS1 C1.10 2E11 UHX-A-3 LOWER SHELL RING TO FLANGE AUG 2 El 1 OWN PRE C -A H2 2E11UHX-B-1 8-1 IS1 C1.20 2E11 UHX-B-1 SHELL HEAD TO UPPER SHELL RING AUG 2 El 1 OWN PRE C -A H2 2E11 UHX-B-2 B-1 IS1 C1 .I0 2E11 UHX-B-2 RING AUG 2 El 1 OWN PRF N m 2 2 5 5 . . .- C -A H2 2E11 UHX-B-3 B-1 IS1 C1.10 2E11 UHX-B-3 LOWER SHELL RING TO FLANGE AUG 2 El I OWN F 2 L N Category, Iso No. IternNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case m o 2 2 5 5 Revision:

1 Category, ItemNO. HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company Period 1 I Iso No. Comp. Desc. Class Summary 1 ComplD 1 System Scope I Method I Procedure Code Case C-B H2 2E11PHX-A-I B-1 A IS1 C2.21 2E11 PHX-A-I INLET NOZZLE TO RHR HX SHELL AUG 2 El 1 OWN PRE C -B HZ 2E11 PHX-A-I-IRS B-1 A IS1 C2.22 2E11 PHX-A-I-IRS INLET NOZZLE INNER RADIUS AUG 2 El 1 OWN PRE C-B H2 2E11 PHX-A-0 ISllMTl B-1 A IS1 C2.21 2E11 PHX-A-0 ISllUTl RHR HX SHELL TO OUTLET NOZZLE AUG 2 El 1 OWN PRE C-B H2 2EllPHX-A-0-IRS ISllUTl B-1 A IS1 C2.22 2E11 PHX-A-0-IRS OUTLET NOZZLE INNER RADIUS AUG 2 El 1 OWN PRE C-B H2 2EllPHX-B-I ISIIMTI B-1 B IS1 C2.21 2E11 PHX-B-I ISIIUTI INLET NOZZLE TO RHR HX SHELL AUG 2 El 1 OWN PRE C-B H2 2E11PHX-B-I-IRS lSllUT1 B-1 B IS1 C2.22 2E11 PHX-B-I-IRS INLET NOZZLE INNER RADIUS AUG 2 El 1 OWN PRE C-B H2 2E11PHX-B-0 B-1 B IS1 C2.21 2E11 PHX-B-0 RHR HX SHELL TO OUTLET NOZZLE AUG 2 El 1 OWN PRE C-B H2 2E11 PHX-B-0-IRS B-1 B IS1 C2.22 2E11 PHX-B-0-IRS OUTLET NOZZLE INNER RADIUS AUG 2 El 1 OWN PRE Page I - I 8/3/2006 1 Period 2 Period 3 3 Revision:

1 HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 1 - 17 81312006 1 Period 1 Period 2 Period 3 N o 2 2 F 2 Category, Iso No. ItemNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure m o 2 2 5 5 5 Code Case 5 z C -C H2 2E11 EHX-A-2s-1 I C3.1 O(2) 2E11 QHX-A-2s-1 UPPER SHELL RING SUPPORT AIJG 2 El I OWN PRE C -C H2 2E11 EHX-A-2s-2 B-1 IS1 C3.1 O(2) 2EllQHX-A-2s-2 UPPER SHELL RING SUPPORT AUG 2 El 1 om PRE C -C H2 2E11EHX-A-2s-3 B-1 IS1 C3 10(2) 2E11 QHX-A-2s-3 UPPER SHELL RING SUPPORT AUG 2 El 1 om PRE C -C H2 2E11 QHX-A-2s-4 ISllMTl B-1 IS1 C3.1 O(2) 2E11 QHX-A-2s-4 UPPER SHELL RING SUPPORT AIJG 2 El 1 OWN PRE C-C H2 2E11 QHX-A-3s-1 B-1 IS1 C3.10(2) 2E1 IEHX-A-3s-1 LOWER SHELL RING SUPPORT AIJG 2 El I om PRE C -C H2 2E11QHX-A-3s-2 B-1 IS1 C3.1 O(2) 2E11 QHX-A-3s-2 LOWER SHELL RING SUPPORT AUG 2 El 1 om PRE - C -C H2 2E11 EHX-A-3s-3 B-1 IS1 C3.1 O(2) 2E11 QHX-A-3s-3 LOWER SHELL RING SUPPORT AUG 2 El 1 om PRE C -C H2 2E11QHX-A-3s-4 8-1 IS1 C3.10(2) 2EllQHX-A-3s-4 LOWER SHELL RING SUPPORT AIJG 2 El 1 om PRE C -C H2 2E11 EHX-B-2s-1 B-1 IS1 C3.1 O(2) 2E11 EHX-B-2s-1 UPPER SHELL RING SUPPORT AIJG 2 El I om PRE C -C H2 2E1 IEHX-B-2s-2 B-1 IS1 C3.1 O(2) 2E11 EHX-B-2s-2 UPPER SHELL RING SUPPORT AUG 2 El 1 om PRE ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - ----------- - - - - --------- - - - - ------------ - - - - - - - - - - - - -s---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----------- - - - - - - - - - - - - ------------ . - - - - - - - - - - - ----- - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Revision:

1 HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 2 - 17 81312006 1 Period 1 Period 2 Period 3 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case C -C H2 2E11 QHX-B-2s-3 B-1 IS1 C3 1 O(2) 2E11 QHX-B-2s-3 UPPER SHELL RING SUPPORT AUG 2 El I om pRE C -C H2 2E11 QHX-B-2s-4 8-1 IS1 C3.1 O(2) 2E11 QHX-B-2s-4 UPPER SHELL RING SUPPORT AUG 2 El 1 om PRE C -C H2 2E11QHX-B-3s-1 B-1 IS1 C3 lO(2) 2E11QHX-B-3s-1 LOWER SHELL RING SUPPORT AUG 2 El 1 om PRE C -C H2 2E11 QHX-B-3s-2 B-1 IS1 C3 lO(2) 2E11QHX-B-3s-2 LOWER SHELL RING SUPPORT AUG 2 El 1 om PRE C -C H2 2E1 IQHX-B-3s-3 B-1 IS1 C3 1 O(2) 2E1 1 QHX-B-3s-3 LOWER SHELL RING SUPPORT AUG 2 El I om PRE C -C H2 2EllQHX-B-3s-4 B-1 IS1 C3 lO(2) 2EllQHX-B-3s-4 LOWER SHELL RING SUPPORT AUG 2 El I om PRE C -C H2 2E11-2RHR-16A-DS-7APL-1 THRU 8 B-14 IS1 C3 20 2E11-2RHR-16A-DS-7APL-1 THRU 8 2E11 -RHR-H321 AUG 2 El 1 om pRE C -C H2 2E11-2RHR-16A-DS-7APS-1 AND 2 ISllMTl 0-1 4 IS1 C3 20 2E11-2RHR-16A-DS-7APS-1 AND 2 2E11 -RHR-H321 AUG 2 El 1 om pRE C -C H2 2E11-2RHR-16A-DS-7PS B-14 IS1 C3 20 2E11-2RHR-16A-DS-7PS 2E11 -RHR-R327 AUG 2 El 1 om PRE C-C H2 2E11-2RHR-16A-HXI-2PL-5 THRU 8 B-26 IS1 C3 20 2E11-2RHR-l6A-HXI-2PL-5 THRU 8 2E11-2RHR-R250 AUG 2 El 1 om pRE o z 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - r N a 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -s---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - -

4 Revision:

1 3 HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company d Page 3 - 17 81312006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case C -C H2 2E11-2RHR-l6A-PD-C-3PL-1 THRU 4 8-29 IS1 C3.20 2E11-2RHR-16A-PD-C-3PL-1 THRU 4 2Ell-RHR-HI80 AUG 2 El 1 ow PRE C -C H2 2E11-2RHR-16A-SH-6PL-1 THRU 8 B-17 IS1 C3.20 2E11-2RHR-16A-SH-6PL-1 THRU 8 2E11 -RHR-R91 AUG 2 El 1 ow PRE C -C H2 2E11-2RHR-16B-DS-5PL-1 THRU 8 0-1 8 IS1 C3.20 2E11-2RHR-16B-DS-5PL-1 THRU 8 2Ell-RHR-R129 AUG 2 El 1 OWN PRE C-C H2 2E11-2RHR-16B-DS-8PS-1 THRU 3 B-18 IS1 C3.20 2E11-2RHR-168-DS-8PS-1 THRU 3 2Ell -RHR-A58 AUG 2 El 1 ow PRE C -C H2 2E11-2RHR-168-HXI-2PL-1 THRU 4 8-30 IS1 C3.20 2E11-2RHR-16B-HXI-2PL-1 THRU 4 2Ell-RHR-R269 AUG 2 El 1 ow PRE C -C H2 2E11-2RHR-l6B-HXI-2PL-5 THRU 8 8-30 IS1 C3.20 2E11-2RHR-16B-HXI-2PL-5 THRU 8 2Ell-2RHR-R269 AUG 2 El I ow PRE C-C H2 2E11-2RHR-16B-SH-6PL-1 THRU 8 8-21 IS1 C3.20 2E11-2RHR-16B-SH-6PL-1 THRU 8 2Ell-RHR-R103 AUG 2 El 1 ow PRE C -C H2 2E11-2RHR-16B-SH-6PS-1 AND 2 8-21 IS1 C3.20 2E11-2RHR-16B-SH-6PS-1 AND 2 2El I-RHR-R103 AUG 2 El 1 ow PRE C -C H2 2E11-2RHR-16B-SH-8PS B-21 IS1 C3.20 2El1-2RHR-16B-SH-8PS 2Ell -RHR-H68 AUG 2 El I OWN PRE C -C H2 2E11-2RHR-20A-D-IOPL-1 THRU 4 B-35 IS1 C3 20 2E11-2RHR-20A-D-1OPL-1 THRU 4 2Ell-RHR-HI63 AUG 2 El I OWN PRE N ~3 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - m o 2 2 z 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - y 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - . - - -

u Revision:

1 HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company 3 Page 4 - 17 8/3/2006 1 Period 1 Period 2 Period 3 NO 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .- 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -.---------- - - . - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case C -C H2 2E11-2RHR-20A-D-10PL-5 THRU 12 6-35 IS1 C3 20 2E11-2RHR-20A-D-1 OPL-5 THRU 12 2Ell -RHR-R231 AUG 2 El I om PRE 6-35 H2 2E11-2RHR-20A-D-1 PS-1 THRU 4 C -C IS1 C3 20 2E11-2RHR-20A-D-1 PS-1 THRU 4 2E11-RHR-HR165

-. AUG 2 El I om PRE C -C H2 2E11-2RHR-20A-PD-A-1 PL-1 THRU 4 6-28 IS1 C3 20 2E11-2RHR-20A-PD-A-1 PL-1 THRU 4 2E11 -RHR-HI82 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-20A-PD-A-8PS-1 AND 2 8-28 IS1 C3 20 2E11-2RHR-20A-PD-A-8PS-1 AND 2 2E11 -RHR-R375 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-20A-PD-C-5PS 6-29 IS1 C3 20 2E11-2RHR-20A-PD-C-5PS 2E11-RHR-HI79 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-20A-PD-C-8PL-1 THRU 4 8-29 IS1 C3 20 2E11-2RHR-20A-PD-C-8PL-1 THRU 4 2Ell-RHR-R374 AUG 2 El 1 om PRE C-C H2 2E11-2RHR-20B-BP-1 PS-1 8-34 IS1 C3 20 2E11-2RHR-20B-BP-1 PS-1 2Ell-RHR-H98 AUG 2 El 1 om PRE C-C H2 2E11-2RHR-20B-BP-IPS-2 B-34 IS1 C3 20 2E11-2RHR-20B-BP-1 PS-2 2Ell -RHR-A50 AUG 2 El 1 om PRE C-C H2 2E11-2RHR-206-0-11 PL-1 THRU 4 6-36 IS1 C3 20 2E11-2RHR-206-D-11 PL-1 THRU 4 2Ell -RHR-HI69 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-206-0-11 PL-5 THRU 12 6-36 IS1 C3 20 2E11-2RHR-206-D-11 PL-5 THRU 12 2E11 -RHR-R241 AUG 2 El 1 om PRE o) o z 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

r) Revision:

1 3 HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company d Page 5 - 17 8/3/2006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case C -C H2 2E11-2RHR-208-PD-8-1 PL-1 THRU 4 8-32 ISI C3.20 2E11-2RHR-208-PD-8-1 PL-1 THRU 4 2E11-RHR-HI90 AUG 2 El I om PRE C -C HZ 2E11-2RHR-208-PD-8-8PL-1 THRU 4 8-32 IS1 C3.20 2E11-2RHR-208-PD-8-8PL-1 THRU 4 2E11 -RHR-R378 AUG 2 El 1 om PRE C -C HZ 2E11-2RHR-208-PD-D-5PS 8-33 IS1 C3 20 2E11-2RHR-208-PD-D-5PS 2E11-RHR-HI87 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-208-PD-D-8PL-1 THRU 4 8-33 IS1 C3.20 2E11-2RHR-208-PD-D-8PL-1 THRU 4 2E11 -RHR-R377 AUG 2 El 1 om pRE C -C HZ 2E11-2RHR-20C-D-1OPL-1 THRU 4 8-37 IS1 C3.20 2E11-2RHR-20C-D-1OPL-1 THRU 4 2E11-RHR-HI68 AUG 2 El 1 om PRE C -C HZ 2E11-2RHR-20C-D-3PS-1 AND 2 8-37 IS1 C3.20 2E11-2RHR-20C-D-3PS-1 AND 2 2E11-RHR-HI67 AUG 2 El I om pRE C -C H2 2E11-2RHR-20C-D-5PS-1 AND 2 8-37 IS1 C3.20 2E11-2RHR-20C-D-5PS-1 AND 2 2Ell-RHR-R238 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-20D-D-1OPL-1 THRU 4 lSllMTl 8-38 IS1 C3.20 2E11-2RHR-20D-D-1 OPL-1 THRU 4 2E11-RHR-HI74 AUG 2 El 1 om pRE C -C H2 2E11-2RHR-20D-D-3PS-1 AND 2 8-38 IS1 C3.20 2E11-2RHR-20D-D-3PS-1 AND 2 2E11-RHR-HI73 AUG 2 El 1 om PRE C -C HZ 2E11-2RHR-20D-D-5PS-1 AND 2 8-38 IS1 C3.20 2E11-2RHR-20D-D-5PS-1 AND 2 2E11 -RHR-R245 AUG 2 El I om pRE v- 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - . - - - . - - - - . O) o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - N m 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

b Revision:

1 HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case

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C -C H2 2E11-2RHR-20-RS-2PL-1 THRU 4 ISIIMTI 6-39 IS1 C3.20 2E11-2RHR-20-RS-2PL-1 THRU 4 2Ell-RHR-H314 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-20-RS-2PS-1 AND 2 6-39 IS1 C3.20 2E11-2RHR-20-RS-2PS-1 AND 2 2Ell -RHR-R317 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-20-RS-5PL-1 THRU 8 6-39 IS1 C3.20 2E11-2RHR-20-RS-5PL-1 THRU 8 2 El 1 AUG OWN PR E C -C H2 2E11-2RHR-24A-BP-7PS-1 AND 2 6-40 IS1 C3.20 2E11-2RHR-24A-BP-7PS-1 AND 2 2E11 -RHR-A177 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24A-HXI-4PS-1 AND 2 6-41 IS1 C3.20 2E11-2RHR-24A-HXI-4PS-1 AND 2 2El1-RHR-HI76 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24A-TS-A-1OPS-1 THRU 3 6-42 IS1 C3.20 2E11-2RHR-24A-TS-A-1 OPS-1 THRU 3 2E11-RHR-HI57 AUG 2 El 1 OWN PRE C-C H2 2E11-2RHR-24A-TS-A-1 OPS-4 6-42 IS1 C3.20 2E11-2RHR-24A-TS-A-1 OPS-4 2Ell-RHR-R225 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24A-TS-A-12PS-1 AND 2 6-42 IS1 C3.20 2E11-2RHR-24A-TS-A-12PS-1 AND 2 2Ell-RHR-H719 AUG 2 El 1 OWN PRE C -C HZ 2E11-2RHR-24A-TS-A-12PS-3 AND 4 6-42 IS1 C3.20 2E11-2RHR-24A-TS-A-12PS-3 AND 4 2E11 -RHR-R226 AUG 2 El 1 OWN PRE C -C HZ 2E11-2RHR-24A-TS-A-17PS 6-43 IS1 C3.20 2E11-2RHR-24A-TS-A-17PS 2Ell-RHR-HI55 AUG 2 El 1 OWN PRE Period 1 I Period 2 Period 3 3 Revision:

1 3 HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company d Page 7 - 17 8/3/2006 ( Period 1 Period 2 Period 3 N o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - F 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - . - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case C -C H2 2E11-2RHR-24A-TS-A-4PS 8-42 IS1 C3.20 2E11-2RHR-24A-TS-A-4PS 2Ell-RHR-H715 AUG 2 El 1 om PRE C -C H2 2E1 I-2RHR-24A-TS-A-6PS 8-42 IS1 C3.20 2E11-2RHR-24A-TS-A-6PS 2E11-RHR-HI58 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-24A-TS-C-1 OPS-1 AND 2 8-44 IS1 C3.20 2E11-2RHR-24A-TS-C-1 OPS-1 AND 2 2E11-RHR-HIS0 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-24A-TS-C-IOPS-3 AND 4 8-44 IS1 C3.20 2E11-2RHR-24A-TS-C-1 OPS-3 AND 4 2E11 -RHR-R221 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24A-TS-C-15PL-1 THRU 4 8-44 IS1 C3.20 2El1-2RHR-24A-TS-C-15PL-1 THRU 4 2Ell -RHR-HR149 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-248-BP-7PS lSllMT1 8-46 IS1 C3.20 2E11-2RHR-24B-BP-7PS 2El I-RHR-A185 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-248-HXI-4PS 8-47 IS1 C3 20 2E11-2RHR-24B-HXI-4PS 2E11-RHR-HI84 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-248-TS-8-IOPS-1 THRU 3 8-48 IS1 C3.20 2E11-2RHR-24B-TS-8-1 OPS-1 THRU 3 2E11-RHR-HI61 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-248-TS-8-1 OPS-4 8-48 IS1 C3.20 2E11-2RHR-24B-TS-8-1 OPS-4 2Ell -RHR-R229 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-248-TS-8-12PS-1 AND 2 8-48 IS1 C3.20 2E11-2RHR-24B-TS-8-12PS-1 AND 2 2E11 -RHR-H718 AUG 2 El 1 OWN pRE a lx lx 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - -

Revision:

1 Category, ItemNO, HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company lso No. Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case C-C H2 2E11-2RHR-24B-TS-B-12PS-3 AND 4 8-48 IS1 C3 20 2E11-2RHR-248-TS-B-12PS-3 AND 4 2El l-RHR-R233 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-246-TS-6-17PS 8-49 IS1 C3.20 2Ell-2RHR-248-TS-B-17PS 2El l-RHR-HI59 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24B-TS-B-4PS 8-48 IS1 C3.20 2Ell-2RHR-248-TS-B-4PS 2Ell -RHR-H714 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24B-TS-B-6PS 8-48 IS1 C3.20 2E11-2RHR-248-TS-B-6PS 2El 1-RHR-HI62 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24B-TS-D-IOPS-1 AND 2 8-50 IS1 C3.20 2E11-2RHR-248-TS-D-1OPS-1 AND 2 2El l-RHR-HI53 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24B-TS-D-10PS-3 AND 4 8-50 IS1 C3.20 2E11-2RHR-248-TS-D-1OPS-3 AND 4 2El 1-RHR-R222 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-24B-TS-D-15PS-1 AND 2 8-50 IS1 C3.20 2E11-2RHR-248-TS-D-15PS-1 AND 2 2El 1-RHR-H717 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-6A-RVD-12PL-1 THRU 8 8-1 5 IS1 C3.20 2E11-2RHR-6A-RVD-12PL-1 THRU 8 2El l-RHR-R291 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-6A-RVD-14PL-1 THRU 8 8-1 5 IS1 C3.20 2E11-2RHR-6A-RVD-14PL-1 THRU 8 2E11 -RHR-R292 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-6A-RVD-1 PL-1 THRU 4 8-1 5 IS1 C3.20 2E11-2RHR-6A-RVD-1 PL-1 THRU 4 2 El 1 AUG OWN PRE Period 1 Period 2 r 2 5 Period 3 3 Revision:

1 w HNP-2 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company 3 Page 9 - 17 8/3/2006 1 Period 1 Period 2 Period 3 N- 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Cornp. Desc.

Class Summary I CornplD I System Scope I Method I Procedure Code Case C -C H2 2E11-2RHR-6A-RVD-7PL-1 THRU 8 6-1 5 IS1 C3.20 2E11-2RHR-6A-RVD-7PL-1 THRU 8 2Ell-RHR-R290 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-6A-TSP-5PL-1 THRU 8 6-1 7 IS1 C3.20 2E11-2RHR-6A-TSP-5PL-1 THRU 8 2Ell-RHR-R93 AUG 2 El 1 OWN PRE C-C H2 2E11-2RHR-6A-TSP-5PS-1 AND 2 6-1 7 IS1 C3.20 2E11-2RHR-6A-TSP-5PS-1 AND 2 2E11 -RHR-R93 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-66-RVD-12PL-1 THRU 8 6-1 9 IS1 C3.20 2E11-2RHR-66-RVD-12PL-1 THRU 8 2Ell-RHR-R296 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-66-RVD-14PL-1 THRU 8 6-1 9 IS1 C3.20 2E11-2RHR-66-RVD-14PL-1 THRU 8 2Ell-RHR-R297 AUG 2 El 1 om PRE C-C H2 2E11-2RHR-66-RVD-3PL-1 THRU 4 ISllMTl 6-1 9 IS1 C3.20 2E11-2RHR-66-RVD-3PL-1 THRU 4 2E11-RHR-HMO AUG 2 El 1 om PRE C-C H2 2E11-2RHR-66-RVD-8PL-1 THRU 8 6-1 9 IS1 C3.20 2E11-2RHR-66-RVD-BPL-1 THRU 8 2Ell-RHR-R295 AUG 2 El 1 om PRE C -C H2 2E11-2RHR-66-TSP-1 PS 8-21 IS1 C3.20 2E11-2RHR-66-TSP-1 PS 2E11 -RHR-H70 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-66-TSP-5PS-1 AND 2 6-21 IS1 C3.20 2E11-2RHR-66-TSP-5PS-1 AND 2 2El I -RHR-H712 AUG 2 El 1 OWN PRE C -C H2 2E11-2RHR-66-TSP-5PS-3 AND 4 6-21 IS1 C3.20 2E11-2RHR-66-TSP-5PS-3 AND 4 2E11 -RHR-R105 AUG 2 El 1 om PRE m o 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - . - - - - - - - . - - - - - - - r 2 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - -

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 2 Basis Doc - Class 3 Page 1 of 4 Rev. 1 Scope The only Class 3 ISI examinations required by IWD are the examination of integrally welded attachments (of supports and restra ints) to the pressure boundary of Class 3 piping and components. Class 3 piping and equipment are defined on the HNP-2 Boundary Diagrams listed below:

HB-21033 Plant Service Water HB-21035 Plant Service Water HB-21039 RHR Service Water HB-26000 Main Steam Relief Valve Lines HB-26019 Jockey Pump Seal Cooling HB-26046 Condensate Transfer HB-26050 Plant Service Water HB-26051 Plant Service Water

For the 4 th Interval, examinations are performed in accordance with IWD-1000 of the 2001 Edition of Section XI with Addenda through 2003. Therefore, the examination scope shall apply to Class 3 systems piping and equipment that support the following safety functions:

1. Reactor shutdown

2. Emergency core cooling

3. Containment heat removal

4. Atmosphere cleanup

5. Reactor residual heat removal.

6. Spent fuel pool residual heat removal.

Exemptions

Per IWD-1220 not all of the integrally welded attachments are subject to examination - some are exempt from the examination requirements. These are:

Integral attachments of suppor ts and restraints on piping that are NPS 4 and smaller.

Integral attachments of suppor ts and restraints on vessels , pump, and valves and their connections in piping NPS 4 and smaller.

Integral attachments located on components in systems (or portions of systems) whose function is not requi red in support of reactor residual heat removal, containment heat removal, and emergency core cooling and that ope rate at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200 0 F. Integral attachments that are inaccessible due to being encased in concrete, buried underground, located inside a penetrat ion, or encapsulated by guard pipe.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 2 Basis Doc - Class 3 Page 2 of 4 Rev. 1 Plant Service Water (PSW) Evaluation Equipment required to be cooled during emergency conditions by PSW includes:

1. HB-21033 describes the Class 3 intake structure Divi sion I and Division II Supply Piping. This is the source of all safety-relate PSW water to the essential components and thus must be included. All of the Class 3 piping is in the examination scope for welded attachments except for 4" and under piping. The 18" discharge from the PSW pumps and the Division I and Division II 30" headers are shown on C-29. C-28 shows the 30" Division I and II supply lines to the point where they go underground..

Also shown is the 30" dilution line out to MOV F310 (Class 0 beyond this valve).

After going underground, an 8" supply line from the 30" Division I supply line enters the Diesel Generator Building through the fl oor and supplies cooling water to Diesel Generator 2A as shown on C-46. Similarly, an 8" supply line from the 30" Division II supply line enters the Di esel Generator Building through the floor and supplies cooling water to Diesel Generator 2C as shown on C-46. C-45 shows the 6" return lines from the two diesel to the building floor.

The 6" Standby Diesel Service Water from the pump to the point it goes underground is shown on C-39. The 6" pipe from the Diesel Generator Building wall (coming from the underground piping) to the HNP-1 Diesel Generator 1B is shown on C-37. C-38 shows the 6" return line from Diesel Generator 1B to the building floor.

2. HB-21035 shows a small portion of 6" line that is a header for the discharge side of the Essential LPCI Inverter Room Coolers. This header turns into Seismic II; therefore, this piping is not safety-related. (Note: H-26904 indicates that the PSW is Seismic I on the inlet side of the Inverter Room coolers).

3. Per HB-26039 (Note 5) there is an NRC commitment to maintain a certain portion of fuel pool cooling piping as Class 3. Per HB-26039 and HB-26050 this is the piping that functions as the fuel pool makeup source from the Plant Service Water system. It includes the piping from Plant Service Water to the point downstream of 2G41-F054 where it becomes imbedded in concrete. This piping is shown on C-17B.

4. HB-26050 describes the cooling water supply to equipment in the reactor building. This 10" supply enters the reactor building through the wall from Division I underground piping as shown on C-49. The lin e branches into a 8" line to fire protection which terminates at valve F 109 and it branches to a 6" line which continues on C-32 to a 4" reducer. The 10" line ties continues from C-49 to C-17.

On C-17 there is a 10" inter tie to Division II (See C-15), a 10" supply to C-17A, a 4" fuel pool make up line that continues on C-17B, and an 8" supply to C-23. The intertie to Division II is described belo

w. On C-17A the 10" line goes though P41-F074 and terminates at a cap. The 8" s upply line on C-23 provides cooling water to the drywell coolers. C-23 also shows the return lines which continue on C-23a and terminate on C-23B where the piping goes underground just past P41-F063. Note:

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 2 Basis Doc - Class 3 Page 3 of 4 Rev. 1 the fuel pool make up line is part of an NRC commitment to maintain the pressure boundary (designated as Class N on HB-26039).

5. HB-26051 describes the cooling water supply to emergency core cooling equipment in the reactor bu ilding. This 10" supply enters th e reactor building through the wall from Division II underground piping as shown on C-15. This piping is exempt except for the 6" supply line up to th e 4" reducer and the 10" intertie line with the Division I supply on HB-26050 (See C-17).

RHR Service Water Evaluation HB-21039 describes the Class 3 intake structure Divi sion I and Division II Supply Piping. The piping is in the examination scope for welded attachments except for 4" and under piping. C-2 and C-3 show inlet piping to RHR Heat Exchanger B001A. C-4 and C-5 show inlet piping to RHR Heat Exchange r B001B. C-7 and C-8 show outlet piping for RHR Heat Exchanger B001A and B001B , respectively. C-9, C-10, and C-11 show the RHR Service Water Pumps and the associ ated piping in the intake structure.

Main Steam Relief Piping Evaluation HB-26000 describes the Main Seam relief Valve piping. Isometric Sketches C-109 through C-124 show the scope of the Class 3 portion of the Main Steam Relief valve piping (supports reactor shutdown). Because of the temperature at which they operate, the pressure and temperature exemption cannot be used. All piping is greater than 4" in diameter thus all welded attachments are in the examination scope.

Fuel Pool Makeup Water HB-26039 indicates that the Fuel Pool Cooling and Cleanup System is out of the ISI scope (designated as Class 0 on the Boundary Diagram). Instead, an Emergency Makeup source is maintained through the Plant Service Water system.

Jockey Pump Seal Cooling Per HB-26019, all piping is 4" and less in diameter.

Condensate Transfer As shown on HB-26026, suction is above the safety-related level.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 2 Basis Doc - Class 3 Page 4 of 4 Rev. 1 EXAMINATION Those integrally welded attachments that meet the following three criteria are subject to examination requirements.

1. The integrally welded attachments are located in systems (or portions of systems) that are shown on the referenced Boundary Diagrams, and

2. the system or portions of systems perform the listed safety functions, and

3. they are not exempt.

Each Category D-A Item is discussed below.

Item D1.10, D1.30, & D1.40

None Identified.

Item D1.20 - Piping

As shown in Schedule Works, Hatch 2 has 133 sets of Class 3 welded attachments. Footnote 3 requires a 10% sample; therefore, 14 sets of welded attachments require examination The cumulative examination percentages meet the requirements of Table IWD-2412-1.

Additionally, examination of an integrally welded attachment is required if the associated component support member has deformation identified during operation, refueling, maintenance, examination, inservice inspection, or testing. An example of component support deformation is broken parts, bent parts, or pulled out parts.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 1 of 13 Rev. 1 SCOPE For the 4 th Interval, the determination of the Class 1, 2, and 3 supports to be examined will be performed using Subs ection IWF of the 2001 Edition of Section XI through the 2003 Addenda. (The rules in IWF are similar to those used during the 3 rd Interval per NRC approved Code Case N-491-1). (Note: IWE supports are not included here).

Per the IWA-9000 Glossary a component support is defined as a metal support designed to transmit loads from a component to the load-carrying building or foundation structure. Component supports include pi ping supports and encompass those structural elements relied upon to support the weight or provide structural st ability to components.

Examinations apply to all component supports that are in the scope of the Class 1, 2, and Boundary Diagrams and are not exempt. Supports exempt from examination requirements are those connected to piping or other items exempted from volumetric, surface, VT-1, or VT-3 examinations by IWX-1220. In addition, portions of supports that are inaccessible by being encased in concrete, buried underg round, or encapsulated by guard pipe are also exempt from the examination requirements of IWF-2000.

Component supports should be selected for examination as follows:

1. Supports should be characterized to iden tify its support type/function. For HNP-2, the support type/functions include the following:

Spring Cans - Supports weight while allowing movement due to thermal changes. Hanger - Supports the weight of the piping system. Restraint/struts - Prevents movement of the piping system in one or more degrees of motion. Anchors - Prevents movement in all six degrees of motion.

2. 25% of the non-exempt Class 1 piping supports, 15% of the non-exempt Class 2 piping supports, and 10% of the non-exem pt Class 3 piping supports shall be examined per Table IWF-2500-1.

3. The supports selected for examination sha ll be prorated such that the individual sample sizes for each system are proportional to the number of non-exempt supports in each system.

4. For multiple components other than piping, within a system of similar design, function, and service, the supports of only one of the multiple component are required to be examined.

HATCH UNIT 2 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 2 of 13 Rev. 1 ISI PLAN TABLES Beginning in 2005, ISI Plan Tables are genera ted by the industry standard ScheduleWorks ISI software. The following tables were ge nerated using a standard format provided by ScheduleWorks. It should be noted that the Scope/Method/Procedure field is for information only. This information may be changed during an outage by IDDEAL users at the site, but it will not be reflected in the ISI Plan until the plan is issued after the outage.

When using these tables the user needs to understand the following symbols:

Scheduled "s" To schedule a component, place the identifier "s" in the required period/outage.

Completed "c" Upon exam completion for a scheduled component and by uploading the outage scope from IDDEAL back to ScheduleWorks, an "s" will be updated to completed "c".

Re-scheduled "r" Once a component has been scheduled, and you wish to reschedule to another outage, replace the scheduled "s" with a rescheduled "r" and enter an "s" in the new outage schedule. Expanded Scope "e" To increase a work scope without taking code credit in the percentage calculations, enter an expanded "e".

Expanded Scope Completed "E" Upon exam completion of an expanded scope and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "E" the exam scope is completed. Additional Scheduled "a" After an initial expanded work scope has been identified and you wish to add an increased expanded work scope, enter an additional expanded scope "a". Additional Completed "A" Upon exam completion of an additional expanded scope and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "A" the exam scope is completed.

Partial "p" To track partially completed component examination requirements enter a partial "p". Deferred "d" Once a component has been scheduled, and you wish to defer the inspection to another Outage, or Period, replace the scheduled "s" with a deferred "d" and enter an "s" in the new Outage. Limited "l" To track limited component examinations or limited completions of requirements enter "l". Multiple Scheduled "b For multiple scheduling of the same component in successive Outages or Period s within an Interval enter "b". Multiple Completed "B" Upon exam completion of a multiple scope in the same Interval and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "B" the exam scope is completed. This multiple scheduling scope will not count as completed for code calculations.

Tickler "t" To track exam scopes or use as reminder or identifier to confirm scheduling enter "t". Successive Exams "h" Successive examinations. Successive Exams Com "H" Upon exam completion of a successive scope and by either uploading the outage scope from IDDEAL or manually changing the letter to an upper case "H" the exam scope is completed.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 3 of 13 Rev. 1 EXAMINATION OF SNUBBERS IWF-1220 of the 2001 Edition of Section XI with Addenda through 2003 requires that the inservice inspection requirements for snubbers be in accordance with the requirements of IWF-5000, which states:

(a) Inservice examinations shall be performed in accordance with ASME/ANSI OM, Part 4, using the VT-3 visual examination method described in IWA-2213.

(b) Inservice tests shall be performed in accordance with ASME/ANSI OM, Part 4.

10 CFR 50.55a(b)(3)(v) provides an alternative to these two requirements. Licensees may use Subsection ISTD, "Inservice Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Power Plants," ASME OM Code, 1995 Edition through the 2003 Addenda, in place of the requirements of IWF-5300(a) and (b) by making appropriate changes to their technical specifications or licensee-controlled documents (if required). Inservice examinations must be performed using the VT-3 visual examination method described in IWA-2213.

However, per IWF-5300(c) integral and non-integral attachments for snubbers including bolting, pins, and clamps, shall be examined in accordance with the requirements of this Subsection (IWF). (Attachments to the pressure boundary such as lugs will be examined per Category B-K, C-C, or D-A). IWF allows a percenta ge of the integral and non-integral attachments for snubbers to be examined as follows:

Attachment welds will be examined in accordance with IWB, IWC, or IWD. The snubber unit including the pins that secure the snubber un it into the support structure will be examined as required by OM requirements. The support structure (bolting, pin, and clamps outside of the snubber unit), will be VT-3 examined and reported as required by IWF. Therefore, for Class 1 snubbers, 25% of the support structures will be scheduled and VT-3 examined; 15% of the Class 2 support structures will be scheduled and VT-3 examined, and 10% of the Class 3 support structures will be scheduled and VT-3 examined. For non-piping snubbers, Footnote 3 of Table IWF-2500-1 must be used to determine the scope.

Personnel performing the VT-3 examinations may be qualified and certified per IWA-

2310 through IWA-2314 (the standard qualification/certification process) or per IWA-2317. IWA-2317 allows the use of plant pers onnel with at least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of plant experience in installation, maintenance, or examination of pumps, valves, and supports to perform the VT-3 examinations. These personnel must have 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of training in the Section XI requirements and procedures for VT-3 visual examinations, meet the vision test requirements of IWA-2321, have an initial exam, and have a followup exam every three years. If using these alternate requirements they shall be described in the appropriate written practice. (Note: The "official" list of sn ubbers is shown in HNP site procedures 52SV-SUV-001-0S and 52SV-SUV-002-0S).

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 4 of 13 Rev. 1 Determination of Class 1 Pi ping Supports to be Examined Per IWF-1230 supports exempt from examinati on are those connected to piping and other items exempted from examination by IWB.

These include supports on lines:

NPS 1" and smaller for Schedule 80 and Schedule 160 water lines.

NPS 2"and smaller for Schedule 80 steam lines and NPS 2.5" for Schedule 160 steam lines. Per Schedule Works there are 80 Category F-A, Item F1.10 piping supports, plus 39 Item F1.10N supports on small diameter lines that were that were exempt during the 3 rd Interval. The "N" designation was used for the new supports added during the 4 th Interval. It should be noted that, in many cases, the HNP-2 design isometric drawing shows a containment penetration as being an anchor point for the purpose of stress analysis because it is a rigid point. This "anchor" is not labeled except for the penetration number and it is not a component support.

Table IWF-2500-1, Category F-A, Item F1.10 requires that 25% of the (80 + 39) non-exempt Class 1 supports be examined (30 supports). Additionally, per Footnote 2 of Table IWF-2500-1, the examinations should be prorated among the Class 1 systems based on the number of supports shown for each system versus the total number of non-exempt supports. These proportional values are listed below for each Class 1 system and are shown as exact values only to eliminate the compounding of round-up/down errors. The number examined for each system may have a slight variance from the prorated number as long as the 30 examinations were performed.

CLASS 1 (Item F1.10) System No. of Non-Exempt Supports in

System Calculated No. of Supports Examined No. of Supports Selected 2B21 51 12.75 12 2B31 12 3 2 2C41 29 7.25 8 2E11 6 1.5 2 2E21 6 1.5 2 2E41 2 0.5 1 2E51 4 1 1 2G31 9 2.25 3 TOTAL 119 29.75 31

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 5 of 13 Rev. 1 Many of these same systems have snubbers. While the examination of the snubber unit is performed per OM, not Section XI; the remainder of the support is effectively examined the same as any other support. As shown in the table below, there are 54 snubbers in the Class 1 piping systems; therefore, 14 require examination per Section XI. The snubbers to be examined are prorated through the Class 1 piping systems as shown below.

CLASS 1 (Item F1.10S) System No. of Non-Exempt Snubbers in

System Calculated No. of Snubbers Examined No. of Supports Selected 2B21 22 5.5 6 2B31 8 2 3 2E11 5 1.25 2 2E21 0 0 0 2E41 6 1.5 2 2E51 3 .75 1 2G31 1 .25 1 TOTAL 54 13.5 15

Because of the potential changes in the snubber population during the 4 th Interval, one additional 2B31 snubber has been added to the examination scope to account for any variances. Since 15 examinations at a 25%

sample rate will cover a population of 60 snubbers, 6 additional snubbers (60-54) would need to be added to the scope before there would be a Code issue.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 6 of 13 Rev. 1 Determination of Class 2 Pi ping Supports to be Examined Per IWF-1230 supports exempt from examinati on are those connected to piping and other items exempted from examination by IWC. These include:

Supports located on components less than or equal to 4" in diameter. (Reference Class 2 portion of this document for IWB-1220 exemptions used at HNP-2).

Supports located on components in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, containment heat removal, and emergency core cooling and that operate at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200 0 F. (Reference Class 2 portion of this document for IWB-1220 exemptions used at HNP-2).

Supports located on components of any size beyond the last shutoff valve in open ended portions of systems that do not contain water during normal operation. (Reference Class 2 portion of this document for IWB-1220 exemptions used at HNP-2). Portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe.

Per Schedule Works there are 326 non-exempt Category F-A, Item F1.20 piping supports (excluding snubbers).

It should be noted that, in many cases, the HNP-2 design isometric shows a containment pene tration, torus penetration, pump nozzle, etc. as being an anchor point for the purpose of stress analysis because it is a rigid point. This "anchor" is not labeled except for the penetration number and it is not a component support.

Table IWF-2500-1, Category F-A, Item F1.20 requires that 15% of the 326 non-exempt Class 2 supports (or 49) be examined. Additionally, per Footnote 2 of Table IWF-2500-1, the examinations should be prorated among the Class 2 systems based on the number of supports shown for each system versus the total number of non-exempt supports. These proportional values are listed below for each Class 2 system and are shown as exact values only to eliminate the compounding of round-up/down errors. The number examined for each system may have a slight variance from the prorated number as long as the 49 examinations were performed.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 7 of 13 Rev. 1 CLASS 2 (Item F1.20) System No. of Non-Exempt Supports in

System Calculated No. of Supports Examined No. of Supports Selected 2E11 132 19.8 19 2E21 75 11.25 11 2E41 63 9.45 10 2E51 1 .15 1 2G51 1 .15 1 2N11 41 6.15 6 2N37 3 .45 1 2T48 10 1.5 1 TOTAL 326 48.9 50

Some of these same systems have snubbers. While the examination of the snubber unit is performed per OM, not Section XI; the remainder of the support is effectively examined the same as any other support. As shown in the table below, there are 102 snubbers in Class 2 piping systems; therefore, about 16 require examination per Section XI. The snubbers to be examined are prorated through the Class 2 piping systems as shown below.

CLASS 2 (Item F1.20S) System No. of Non-Exempt Snubbers in

System Calculated No. of Snubbers Examined No. of Supports Selected 2E11 58 8.7 10 2E21 9 1.35 2 2E41 9 1.35 1 2N11 22 3.3 4 2T48 4 .6 1 TOTAL 102 15.3 18

Because of the potential changes in the snubber population during the 4 th Interval, one additional 2E11 snubber examination has been added to the examination scope to account for any variances. This additional weld plus one extra examination due to roundup yields an excess of 2 examinations. Since 18 examinations at a 15% sample rate will cover a

population of 120 snubbers, 18 additional snubber s (120-102) would need to be added to the scope before there would be a Code issue.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 8 of 13 Rev. 1 Determination of Class 3 Pi ping Supports to be Examined Per IWF-1230 supports exempt from examinati on are those connected to piping and other items exempted from examination by IWC. These include:

Supports located on components less than or equal to 4" in diameter. (Reference Class 3 portion of this document for IWB-1220 exemptions used at HNP-2).

Supports located on components in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, containment heat removal, and emergency core cooling and that operate at a pressure equal to or less than 275 psig and at a temperature equal to or less than 200 0 F. (Reference Class 2 portion of this document for IWB-1220 exemptions used at HNP-2).

Portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe.

Per Schedule Works there are 295 non-exempt Category F-A, Item F1.30 piping supports (excluding snubbers).

It should be noted that, in many cases, the HNP-2 design isometric shows a pump nozzle, etc.

as being an anchor point for the purpose of stress analysis because it is a rigid point. This "anchor" is not labeled except for the penetration number and it is not a component support.

Table IWF-2500-1, Category F-A, Item F1.30 requires that 10% of the 295 non-exempt Class 3 supports be examined. Therefore, at least 30 Class 3 piping supports are required to be examined. Additionally, per Footnote 2 of Table -2500-1, the examinations should be prorated among the Class 3 systems based on the number of supports shown for each system versus the total number of non-exempt supports. These proportional values are listed below for each Class 3 system and are shown as exact values only to eliminate the compounding of round-up/down errors. The number examined for each system may have a slight variance from the prorated number as long as the 30 examinations were performed.

CLASS 3 (Item F1.30) System No. of Non-Exempt Supports in

System Calculated No. of Supports Examined No. of Supports Selected 2B21 64 6.4 7 2E11 66 6.6 7 2G41 9 .9 1 2P41 156 15.6 16 TOTAL 295 29.5 31

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 9 of 13 Rev. 1 Many of these same systems have snubbers. While the examination of the snubber unit is performed per OM, not Section XI; the remainder of the support is effectively examined the same as any other support. As shown in the table below, there are 37 snubbers in Class 3 piping systems; therefore, 4 require examination per Section XI. The snubbers to be examined are prorated through the Class 3 systems as shown below.

CLASS 3 (Item F1.30S) System No. of Non-Exempt Snubbers in

System Calculated No. of Snubbers Examined No. of Supports Selected B21 63 6.3 7 TOTAL 63 6.3 7

Because of the potential changes in the snubber population during the 4 th Interval the number of snubbers selected was rounded up to

7. This would allow the addition of 7 Class 3 snubbers before there would be a Code issue.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 10 of 13 Rev. 1 Determination of Supports Other Than Piping to be Examined Per Schedule Works there are 62 non-exempt Category F-A, Item F1.40 equipment supports. These 62 supports are shown in the below listed table. Table IWF-2500-1 requires the examination of each equipment support except when there are multiple components within a system that have a sim ilar design, function, and service. For this case, Note 3 of Table 2500-1 indicates that only the supports on one of the similar components needs to be examined. For example each of the two RC pumps has three supports for a total of six supports. Only three of the supports are required to be examined. The examination selection is listed in the table shown below.

The support structure around each RPV stabilizer brackets was not included as a support, because there are no loads transmitted to them unless there is movement of the RPV due to a significant seismic event.

They are considered analogou s to pipe whip restraints which are not included as supports (See Interpretation XI-80-02).

Interpretation Number: XI-80-02 Date: 10-APR-80

Subject:

Section XI, Division 1, IWF-1100, Examination of Pipe Restraints Question: DoesSection IX, Division 1, IWF-1100 exclude pipe whip restraints from the inservice inspection requirements of Subsection IWF?

Reply: The scope of IWF is limited to those supports which are required to be constructed in accordance with Subsection NF. Since pipe whip restraints are exempt from the requirements of NF, they are also exempt from the requirements of IWF.

The Recirculation Pumps are the only Class 1, 2, or 3 equipment that has snubbers. While the examination of the snubber unit is performed per OM, not Section XI; the remainder of the support is effectively examined the same as any other support. There are six snubbers on each pump, with only the snubbers on one of the pumps requiring examination.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 11 of 13 Rev. 1 Equipment Supports (Excluding Snubbers) Code Case N-491 Item F1.40 Component Fig Description P1 P2 P3 Notes 2B11-A001-S01 2B11-SK1 RPV Skirt X 2B31-HA5 A-16 RC PUMP A - SPRING 2B31-HA6 A-16 RC PUMP A - SPRING 2B31-HA7 A-16 RC PUMP A - SPRING X 2B31-HB5 A-18 RC PUMP B - SPRING 2B31-HB6 A-18 RC PUMP B - SPRING 2B31-HB7 A-18 RC PUMP B - SPRING 2C41-A001-S01 2C41-SK2 Tank X 2C41-C001A-S01 2C41-SK3 SBLC Pump X 2C41-C001B-S01 2C41-SK3 SBLC Pump 2E11-B001A-S01 2E11-SK4 RHR Heat Exchanger X 2E11-B001B-S01 2E11-SK4 RHR Heat Exchanger 2E11-C002D-S01 2E11-SK5 RHR Pump 2E11-C002A-S01 2E11-SK5 RHR Pump X 2E11-C002B-S01 2E11-SK5 RHR Pump 2E11-C002C-S01 2E11-SK5 RHR Pump 2E21-C001B-S01 2E21-SK6 CS Pump 2E21-C001A-S01 2E21-SK6 CS Pump X 2E41-C001-S01 2E41-SK7 HPCI Pump X 2E51-C001-S01 2E51-SK8 RCIC Pump X 2T47-B007A-S01 2T47-SK9 Cooling Unit X 2T47-B007B-S01 2T47-SK9 Cooling Unit 2T47-B008A-S01 2T47-SK9 Cooling Unit 2T47-B008B-S01 2T47-SK9 Cooling Unit 2T47-B009A-S01 2T47-SK9 Cooling Unit 2T47-B009B-S01 2T47-SK9 Cooling Unit 2T47-B010A-S01 2T47-SK9 Cooling Unit 2T47-B010B-S01 2T47-SK9 Cooling Unit 2E11-C001A-S01 2E11-SK10 RHRSW Pump X 2E11-C001A-S02 2E11-SK10 RHRSW Pump 2E11-C001B-S01 2E11-SK10 RHRSW Pump 2E11-C001B-S02 2E11-SK10 RHRSW Pump

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 12 of 13 Rev. 1 Equipment Supports (Excluding Snubbers) Code Case N-491 Item F1.40 Component Fig Description P1 P2 P3 Notes 2E11-C001C-S01 2E11-SK10 RHRSW Pump 2E11-C001C-S02 2E11-SK10 RHRSW Pump 2E11-C001D-S01 2E11-SK10 RHRSW Pump 2E11-C001D-S02 2E11-SK10 RHRSW Pump 2E11-D002A-S01 2E11-SK11 RHRSW Strainer X 2E11-D002B-S01 2E11-SK11 RHRSW Strainer 2E11-D003A-S01 2E11-SK11 RHRSW Strainer 2E11-D003B-S01 2E11-SK11 RHRSW Strainer 2P41-C001C-S01 2P41-SK12 PSW Pump 2P41-C001D-S02 2P41-SK12 PSW Pump 2P41-C001C-S02 2P41-SK12 PSW Pump 2P41-C001B-S02 2P41-SK12 PSW Pump 2P41-C001B-S01 2P41-SK12 PSW Pump 2P41-C001A-S02 2P41-SK12 PSW Pump 2P41-C001A-S01 2P41-SK12 PSW Pump X 2P41-C001D-S01 2P41-SK12 PSW Pump 2P41-C002-S02 2P41-SK13 Standby PSW Pump X Different Pump Type Than C001 Pum p s2P41-C002-S01 2P41-SK13 Standby PSW Pump Different Pump Type Than C001 Pumps 2P41-D001A-S01 2P41-SK14 PSW Strainer X 2P41-D001B-S01 2P41-SK14 PSW Strainer 2P64-B006B-S01 2P64-SK15 Chiller-Condenser 2P64-B006A-S01 2P64-SK15 Chiller-Condenser X 2T41-B002A-S01 2T41-SK16 RHR/CS Room Cooler X 2T41-B002B-S01 2T41-SK16 RHR/CS Room Cooler 2T41-B003B-S01 2T41-SK17 RHR/CS Room Cooler 2T41-B003A-S01 2T41-SK17 RHR/CS Room Cooler 2T41-B005B-S01 2T41-SK18 HPCI Room Cooler 2T41-B005A-S01 2T41-SK18 HPCI Room Cooler 2Z41-B020A-S01 2Z41-SK19 LPCI Inv Room Cooler X 2Z41-B020B-S01 2Z41-SK19 LPCI Inv Room Cooler TOTAL-62 5 7 6 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 2 Basis Doc -Supports.doc Page 13 of 13 Rev. 1 TOTAL CLASS 1, 2, AND 3 PIPING SUPPORTS AND EQUIPMENT SUPPORTS Code requirements were met as shown in the Code Compliance Scheduling Summary for F-A supports and snubbers.

SCOPE EXPANSION Component support examinations that reveal flaws or relevant conditions exceeding the acceptance standards of IWF-3400 shall be extended to include the component supports immediately adjacent to those component supports for whic h corrective action is required. Additional examinations shall be extended to include additional supports within the same system, equal in number and of the same type and function as those scheduled for examination during the period.

Alternately, per IWF-3122.3 the component suppor t with the flaw or relevant condition may be accepted for continued service without corrective actions if an evaluation or test demonstrates that the component support is acceptable for service. Since corrective actions are not required, scope expansion is not required.

SUCCESSIVE EXAMINATIONS Acceptance of IWF-3410 Conditions by Corrective Measures or Repair Replacement Per IWF-2220(a), when a component support is accepted for continued service by corrective measures (e.g., adjustment for conditions such as loosened mechanical connections, improper hot/cold settings, etc.)

or is accepted through repair/replacement activities the component support shall be re-examined prior to returning the system to service.

Per IWF-2220(b), when a component support is in a system that operates above 200 0 F and is accepted for continued service by corrective measures (e.g., adjustment for conditions such as loosened mechanical connections, improper hot/cold settings, etc.) or is accepted through repair/replacement activities the com ponent support shall be re-examined during the following heatup and cooldown cycle unless determined unnecessary by evaluation. This examination shall be performed during operation or the next refueling outage.

Per IWF-2420, the component support shall also be re-examined during the next inspection period.

Acceptance of IWF-3410 Conditions by Evaluation or Test

When a component support is accepted for continued service by evaluation or test in accordance with IWF-3122.3 re-examination is not required during the ne xt inspection period. If evaluated or tested and determin ed acceptable for conti nued service corrective measures may be used to restore the s upport to it original design condition re-examination is not required prior to returning the system to service.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 1 of 40 Rev.1.0 SCOPE This report describes the revised inspection criteria for stainless steel and dissimilar metal weld piping subject to Generic Letter 88-01, "NRC Position on Intergranular Stress Corrosion Cracking in BWR Austenitic Stainless Steel Piping" requirements based on the revised criteria in BWRVIP-075.

Included are new inspection frequencies and new sample expansion criteria.

BACKGROUND Due to extensive Intergranular Stress Corrosion Cracking (IGSCC), the stainless steel piping for the Recirculation System, the RHR System, and the RWCU System was replaced with IGSCC resistant 316NG material during the mid-1980's. However, components such as the stainless steel RPV safe-ends and the RWCU containment pe netration piping were not replaced. Each of the welds (where the configuration allowed) was subsequently stress improved to reduce the tensile residual stresses at the weldment inside surface. An inspection program was set up per the requirements Generic Letter 84-11 which was subsequently superseded by Generic Letter 88-01 (GL 88-01), "NRC Position on Intergranular Stress Corrosion Cracking in BWR Austenitic Stainless Steel Piping" and NUREG-0313, "Technical Report on Material Se lection and Processing Guidelines for BWR Coolant Pressure Boundary Piping". Insp ection Categories were established based on GL 88-01 requirements. GL 88-01 Categories currently applicable to HNP-2 are:

Category A - Welds are made from materials that are resistant to IGSCC due to their metallurgical properties. As such, the current required inspection sc ope and frequency per GL 88-01 is 25% of the population every 10 years.

Category C - Welds are made from material that is considered susceptible to IGSCC, but the IGSCC was mitigated by stress improvement after more than two cycles of operation. GL 88-01 specifies that the entire population is to be examined once every ten years.

Category D - Welds are those made of susceptible material that have not been treated with an IGSCC remedy and in which cracks have not been reported. GL 88-01 specifies that all welds be examined every two refueling cycles.

Category E- Welds that have been overlayed with IGSCC resistant material. GL 88-01 specifies that all overlays be examin ed every two refueling outages.

Because of improved water chemistry that significantly reduced the propensity for initiation and growth of IGSCC, and due to improved examination procedures/techniques for the detection and sizing of IGSCC, new inspection criteria were proposed in BWRVIP-075 and subsequently accepted by the NRC for each of these categories. This report describes the

revised inspection criteria for Category A, Category C, Cate gory D, and Category E piping subject to GL 88-01 requirements based on the revised criteria in BWRVIP-075. Included are new inspection frequencies and new sample expansion criteria. Table 1 lists key dates FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 2 of 40 Rev.1.0 and actions associated with the transition from GL 88-01 to BWRVIP-075 requirements at HNP-2.

Table 1 Transition From GL-88-01 To BWRVIP-05 DATE ITEM 6/23/2000 HNP requested the use of BWRVIP-075 in lieu of GL 88-01 and requested an alternative to Code requirements to allow reduced B-J and B-F Code requirements. 10/10/2000 The NRC issued a safety evaluation for the HNP request allowing HNP a one cycle use of BWRVIP-075 in lieu of GL 88-01 and Code relaxation from B-F (100%) and B-J (25%) provided that surface examinations were performed. 10/2000 The NRC issued a safety evaluati on (with caveats) allowing the use of BWRVIP-075 in lieu of the existing GL 88-01 requirements. The NRC noted that the safety evaluation could be used as a reference for a 10CFR50.55a alternative to reduce Code exams for welds in GL 88-01 scope. 6/2001 Structural Integrity Associates issues "Weld Prioritization for Adoption of BWRVIP-075 at Edwin I. Hatch Unit 1 and Unit 2". 5/2002 The NRC issues the final BWRVIP-075 safety evaluation after evaluation of BWRVIP responses to open items. 4/2003 The BWRVIP issues the initial draft A-Version of BWRVIP-075 to incorporate the NRC's comments in their final safety evaluation. 2004 SNC seeks approval in RR-39 to reduce the Code exams associated with this piping. 7/2005 NRC grants approval of RR-39. 10/2005 BWRVIP-75-A Final report issued. 12/2005 NRC grants approval of ISI-ALT-3 to continue during the 4 th Interval with the alternatives originally set forth in RR-39. 3/2006 NRC issues approval letter for BWRVIP-75-A. 4/2006 EPRI issues letter from Robin Dyle/Tom Mulford regarding inspection relief for hydrogen water chemistry.

VIP-75 IMPLEMENTATION The NRC issued a final Safety Evalua tion for BWRVIP-075 dated May 14, 2002 with several comments. Subsequently, the BWRVIP developed a draft version of BWRVIP-075-A to incorporate the NRC comments and this document was found acceptable by NRC letter dated March 16, 2006.

This bases document is based on BWRVIP-75-A dated October 2005.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 3 of 40 Rev.1.0 The sample size required to be examined by BWRVIP-075-A is smalle r than that required by ASME Section XI. Therefore, ISI-ALT-3 was submitted to the NRC and subsequently approved by an NRC Safety Evaluation dated 12/

22/05. This request allows the use of the new sample sizes specified in BWRVIP-075 as an alternativ e to 10 CFR 50.55a and Section XI Code requirements for Category B-J and B-F welds.

Note:

The associated ScheduleWorks Tables have been assigned an Item Number equivalent to the Table Numbers listed in the below write-up to allow comparison of the written text to the ScheduleWorks Tables.

For example, Table 2 in the below written te xt and tables lists 67 Category A welds. There is an equivalent Item Number desi gnated as "Table 2" in the ScheduleWorks Tables with 67 welds.

Evaluation of OE22809- Operating Experience where Perry GL 88-01 Exams Were Not Performed Within Required Frequency. Dated 6/19/2006 Upon receipt of a letter from the Boiling Water Reactor Vessel and Internals Project (BWRVIP) alerting utilities th at they should ensure that generic inspection relief for Hydrogen Water Chemistry is not being taken, the implementation of Generic Letter (GL) 88-01 inspection schedules, as modified by EPRI Technical Report TR-113932, "BWR Vessel and Internals Project Technical Basi s for Revisions to Generic Letter 88-01 Inspection Schedules (BWRVIP-75)," was revi ewed by Perry and it was found that a GL 88-01 Category E weld had been erroneously put on a 10 year schedule rather than the required six year schedule. Examination of the weld by the six year point was missed.

Discovery of this scheduling error resulted in a full review of the scheduling for GL 88-01 exams. The review found that GL 88-01 Category C weld examinations, identified as having an "every 10 years" frequency in GL 88-01 and BWRVIP-75, had been incorporated into Perry's augmented Inservice examination program on a "10-year interval" frequency consistent with normal ASME Section XI schedul ing. That is, they were scheduled to meet Section XI successive examination requirements, which allow for extension by as much as a year to enable an inspection to coincide with an outage. As such, some Category C welds were not examined by the 10 year point, which was in-between refueling outages, and thus did not meet a literal interp retation of "every 10 years." SNC Position - SNC has specific relief as defined in Appendix B of this document.

Regarding the "every 10 years" versus the "10-year interval" freque ncy, Robin Dyle who is the author of BWVIP-075 stated that it was his in tent to use a 10-year interval frequency as defined in Section XI. Therefore, the length of time to perform an examination can be up to 11 years if needed to coincide with a scheduled outage.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 4 of 40 Rev.1.0 Review of SNC Scheduling Table 2 includes 67 Category A welds with hydroge n water protection. A 10% sample was used; therefore, 7 welds were selected and will be examined on a 10-year interval frequency. Three welds were examined in Spring 2000 and will be re-examined Spring 2009; one weld was examined in Spring 2003 and will be re-examined in 2009; and three welds were examined in Spring 2005 and will be re-examined in Spring 2015.

Table 3 includes 12 Category C welds without effective hydrogen water chemistry. A 25% sample was used; therefore 3 welds were selected and will be examined on a 10-year interval frequency. Two welds were examined in Spring 2000 and will be re-examined in Spring 2009. One weld was examined in Spring 2005 and will be re-examined in Spring 2015. Table 4 includes 12 Category C welds with effective hydrogen water chemistry. A 10% sample was used; therefore 2 welds were selected and will be examined on a 10-year interval frequency. Two welds were examined in Spring 2005 and will be re-examined in Spring 2015.

Table 5 includes 5 Category welds without effective hydrogen water chemistry. A 25% sample was used; therefore 2 welds were selected and will be examined on a 10-year interval frequency. Two were examined in Spring 2000 and will be re-examined in 2009.

Table 6 includes 18 Category C welds with effective hydrogen water chemistry. A 10% sample was used; therefore 2 welds were selected and will be examined on a 10-year interval frequency. Two were examined in Spring 2000 and will be re-examined in 2009.

Table 7 includes 4 Category D welds without effective hydrogen water chemistry. These four welds are listed as Category D because there is a potential that they are not fully stress improved. The three RHR welds were examined in 2005 and are scheduled for examination every 2 nd outage (2009 and 2013). The feed water weld is a special case because it cannot be inspected per Appendix VIII since it adjoins a weld overlay. It is conservatively listed as Category D because of relaxation issues due to the application of the adjacent weld overlay; however, some compressive forces will be observed at the ID due to the overlay. An Appendix VIII, automated examination will be attempted in 2009. Future recommendations will be made at that time.

Table 8 includes one Category E overlaid weld without effective hydrogen water chemistry. It will be examined on a 10-year interval frequency. This overlay was examined in 2005 and will be re-examined in 2015.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 5 of 40 Rev.1.0 CATEGORY A WELDS The materials in Category A are resistant to IGSCC due their metallurg ical properties. As such, the current required inspection scope and frequenc y per NUREG-0313 and GL 88-01 is 25% of the population every 10 years.

New Category A Examination Frequency Per BWRVIP-075-A, the new examination freque ncy for Category A welds is a function of their ASME Section XI Code classification.

B-F Scope (N/A to Hatch 2)

Category A welds, that are currently classified asSection XI Category B-F welds, will be examined at a rate of 25% over ten years. For welds that are protected by effective HWC, the BWRVIP proposed that the sample size for Category B-F welds is 10%. Fifty percent (50%) of these examinations must be complete d during the first six ye ars of the ten-year interval.

Hatch 2 does not have any welds with this designation.

B-J Scope The BWRVIP proposed that weld s that are currently classi fied as Category A and are classified asSection XI Category B-J per Section XI be examined at a rate of 10% over ten years. Fifty percent (50%) of these examinations must be completed during the first six years of the ten-year interval.

New Category A Scope of Examinations As shown in Table 2, there are 67 HNP-2 Cate gory A welds; therefore seven welds require examination during the 4 th Interval. Four of these welds must be examined prior to the end of 2011.

Risk Insights Used During Se lection of the Category A Welds Per Section 4.1 of BWRVIP-75-A the most risk significant piping is the reactor coolant pressure boundary that supports the ECCS function or containment outside the drywell and that are subject to thermal fatigue or crevice corrosion in addition to IGSCC. Piping that functions only as the RCPB would generally have lower risk.

As shown in Table 2, there are 30 Category A HNP-2 welds that form the pressure

boundary for RHR Injection (which is an ECCS function). None of the welds have an outboard containment isolation function or have been identified as being susceptible to thermal fatigue. Therefore, the welds to be examined will be selected out of the 30 weld

ECCS subset. Twenty-four welds are located in the Reactor Recirculation system on the FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 6 of 40 Rev.1.0 12" risers, the 22" headers, and the 28" piping downstream of the 2B31-F031A&B valves. Six welds are located in the RHR LPCI lines.

Category A Weld Selection Per Section 4.1 of BWRVIP-75-A, during the selection of locations for inspection, consideration should be given regarding locations where IGSCC could be accelerated by crevice corrosion or thermal fatigue. In addi tion, locations having at tributes that would promote IGSCC should have higher priority for inspection. The attributes that may be considered include: high carbon or low ferrite co ntent, crevice or sta gnant flow conditions, evidence of weld repair, surface cold work, and high fit-up, residual and operating stresses.

For the 24 Reactor Recirculation system welds that have an ECCS function, all have received an effective stress improvement and all are subject to effective hydrogen water chemistry (HWC). For the 6 RHR welds all received an effective stress, but none are subject to effective HWC because they are located in stagnant lines.

In the report, "Weld Prioritization for Adopti on of BWRVIP-075 at Edwin I. Hatch Unit 1 and Unit 2", dated June 2001, Structural Integrit y Associates (SIA) st ated in Section 3.0, Weld Selection Process that, "consideration should be given to those locations having attributes that would promote IGSCC, or where IGSCC could be accelerated by crevice corrosion or thermal fatigue. These attributes include: high carbon or low ferrite content, crevice or stagnant flow conditions, evidence of weld repair, surfac e cold work, and high fit-up, residual and operating stresses. Each weld was assigned a rank of 1 to 5, with a Priority 1 being considered to be the most susceptible to IGSCC. These attributes are very similar to those in BWRVIP-75-A; therefore, the SIA document was used for guidance in selecting welds. This prioritization is shown in column 4 (S IA Priority) of Table 2. The welds in Table 2 were designated by SIA as either Priority 2 or Priority 4.

Two Priority 4 welds in the RHR lines were selected even though they had a lower SIA priority because they are located in stagnant flow lines and ar e not subject to the additional mitigating effects of HWC. Five Priority 2 welds in the Recirculation system (with effective HWC) were also selected. F our welds (57%) were selected for the 1 st Period and three welds (43%) were selected for the 3 rd Period. New Category A Scope Expansion The sample expansion criteria to be used for Category A are similar to those specified in GL 88-01. If one or more welds are determined to be cracked by this examination program, an additional sample of equal size and approximately the same distribution will be examined during the same outage. If cracking is detected in the second sample, 25% of the remaining population will be examined. If a dditional cracking is detected, the entire Category A population will be examined. The size or distribution of the expanded sample may be altered if technical justification exists. If this option is used, the NRC will be notified when the expanded scope examinations begin.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 7 of 40 Rev.1.0 CATEGORY C WELDS Category C welds are made from material that is considered susceptible to IGSCC, but mitigated by stress improvement after more than two cycles of operation. GL 88-01 specifies that the entire population is to be examined once every ten years.

New Category C Examination Frequency Category C welds that satisfy the following criteria may be examined at a rate of 25% per ten years. The licensee must ensure that an effective stress improvement was achieved. Additionally, there must have been either:

a) a preservice (post-stress improvement) and inservice examination with a qualified procedure with no cracking identified, or b) For welds that were stress improved prior to the publication of BWRVIP-75-A but did not receive a preservice examination, at least one examination performed with a qualified procedure after more than two operating cycles and no cracking detected.

With effective hydrogen water chemistry (HWC), the scope may be further reduced to 10%

of the population.

For HNP-2, each Category C weld has had an effective stress improvement and received a post-stress improvement examination and with at least one examination using qualified procedures. See Appendix A for the basis for Qualified Examinations and Appendix C for the basis for Effective Stre ss Improvement. New Category C Scope of Examinations Category C welds consist of similar metal (SM) welds and dissimilar metal (DM) welds, and are listed in the following tables:

Table 3 - DM Welds With Effective Stress Improvement Without Effective HWC Table 4 - DM Welds With Effective Stress Improvement With Effective HWC Table 5 - SM Welds With Effective Stress Improvement Without Effective HWC Table 6 - SM Welds With Effective Stress Improvement With Effective HWC Risk Insights Used During Se lection of the Category C Welds Per Section 4.1 of BWRVIP-75-A the most risk significant piping is the reactor coolant pressure boundary that supports the ECCS function or containment outside the drywell and that are subject to thermal fatigue or crevice corrosion in addition to IGSCC. Piping that functions only as the RCPB woul d generally have lower risk.

Applicable ECCS functions for this piping are HPCI, RHR Injection, and Core Spray. None of the welds have an outboard containment isolation function or have been identified as being susceptible to thermal fatigue.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 8 of 40 Rev.1.0 Category C Weld Selection Per Section 4.1 of BWRVIP-75-A, during the selection of locations for inspection, consideration should be given regarding locations where IG SCC could be accelerated by crevice corrosion or thermal fatigue. In addi tion, locations having at tributes that would promote IGSCC should have higher priority for inspection. The attributes that may be considered include: high carbon or low ferrite co ntent, crevice or sta gnant flow conditions, evidence of weld repair, surface cold work, and high fit-up, residual and operating stresses.

In the report, "Weld Prioritization for Adopti on of BWRVIP-075 at Edwin I. Hatch Unit 1 and Unit 2", dated June 2001, Structural Integrit y Associates (SIA) st ated in Section 3.0, Weld Selection Process that, "consideration should be given to those locations having attributes that would promote IGSCC, or where IGSCC could be accelerated by crevice corrosion or thermal fatigue. These attributes include: high carbon or low ferrite content, crevice or stagnant flow conditions, evidence of weld repair, surfac e cold work, and high fit-up, residual and operating stresses. Each weld was assigned a rank of 1 to 5, with a Priority 1 being considered to be the most susceptible to IGSCC. These attributes are very similar to those in BWRVIP-75-A; therefore, the SIA document was used for guidance in selecting welds. All dissimilar metal welds are Priority 1; therefore, the following additional information was considered:

1. Issues with previous examinations based on a review of the previous data by Level III personnel. (See Column 2).

2. Issues with weld crowns or taper that would prevent an Appendix VIII examination from being performed. (See Column 3).

3. Evidence of Repair Work. (See Column 4).

The weld selection are discussed below.

Table 3 - There are 12 dissimilar metal welds that had an effective stress improvement mitigator as defined in Appendix C but do not have effective hydrogen water chemistry as defined in Appendix B. (The Feedwater we lds may not have effective hydrogen water chemistry because there may be insufficient time for proper mixing from the injection point to these welds. The CRD weld and the Core Spray welds are in stagnant lines). Those welds highlighted in yellow are the "one or more" prerequisite examinations with a "qualified" procedure (as defined in Appendix A) prior to implementing the reduced scope. The ECCS welds are the seven Feedwater we lds which form a porti on of the pressure boundary for HPCI and the two Core Spray welds. The sample size is 25% or three welds. Two Feedwater welds were selected during the 1 st Period and two Core Spray welds were selected for examination during the 3 rd Period.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 9 of 40 Rev.1.0 Table 4 - There are 12 dissimilar metal welds that had an effective stress improvement mitigator as defined in Appendix C and have effective hydrogen water chemistry as defined

in Appendix B. Those welds highlighted in yellow are the prerequisite examinations with a "qualified" procedure (as defined in Appendix A) prior to implementing the reduced scope.

The ECCS welds consist of the 10 safe-end to nozzle welds which form a portion of the pressure boundary for LPCI. Six of th e welds 2B31-1RC-12AR-F-5, 2B31-1RC-12AR-H-5, 2B31-1RC-12AR-J-5, 2B31-1RC-12BR-B-5, 2B31-1RC-12BR-C-5, and 2B31-1RC-12BR-D-5 had records of repair by Combustion Engineering. The sample size is 10% or two welds. Two of the six welds were selected during the 3 rd Period.

Table 5 - There are 5 similar metal welds that had an effective stress improvement mitigator as defined in Appendix C but do not have effective hydrogen water chemistry as defined in Appendix B. (The Feedwater we lds may not have effective hydrogen water chemistry because there may be insufficient time for proper mixing from the injection point to these welds. The Jet Pump welds are in stagnant lines). Those welds highlighted in yellow are the prerequisite examinations w ith a "qualified" procedure (as defined in Appendix A) prior to implementing the reduced scope. The ECCS welds are the three Feedwater welds which form a portion of the pressure boundary for HPCI. The sample size is 25% or two welds. Two Feedwater welds were selected during the 1 st Period.

Table 6 - There are 18 similar metal welds that had an effective stress improvement mitigator as defined in Appendix C and have effective hydrogen water chemistry as

defined in Appendix B. Those welds highlighted in yellow are the prerequisite examinations with a "qualified" procedur e (as defined in Appendix A) prior to implementing the reduced scope. The ECCS welds consist of the ten 12" Recirculation system riser welds which form a portion of the pressure boundary for LPCI. Additionally, there are two RWCU welds (2 G31-1RWCUM-6-D-15 and 16) that are located outside of containment. The sample size is 10% or two welds. Two 12" welds were selected during the 1 st Period. Additionally, welds 2G31-1RWCUM-6-D-15, 16, and 17 are high-energy lines in a "no-break" zone that must be examined each ten years. Therefore, five welds will be examined during the 4 th Interval.

Summary The number of welds to be examined for each table was calculated based on the 10% or 25% criteria. The number of welds to be examined within a table is the calculated value rounded up to the next whole number. Because each table is rounde d up, conservatism is built into the sample size as shown below.

There are 17 Category C welds (see Tables 3 and 5) that do not have hydrogen water protection and that are in the 25% sample (5 welds). Within this group there are 10 Feedwater ECCS welds, 2 Core Spray ECCS welds, 4 RC non-ECCS welds, and 1 CRD non-ECCS weld. Selecting from the ECCS scope, as required by BWRVIP-75-A, welds 2B21-1FW-12AB-11, 2B21-1FW-12AB-12 , 2B21-1FW-12AB-13 , and 2B21-1FW-12BD-9 were selected for examination during the 1 st Period of the 4 th Interval. Welds 2E21-1CS-FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 10 of 40 Rev.1.0 10A-21 and 2E21-1CS-10B-20 were selected for the 3 rd Period. Additionally, weld 2B21-1FW-12AA-8 will be re-examined in 2R20. Therefore, 7 welds or 41% of the scope of welds without hydrogen water protection will be examined during the 4 th Interval.

There are 30 Category C welds (see Tables 4 and 6) that have effective hydrogen water protection and that are in the 10% sample (3 welds). Within this group there are 20 RC ECCS welds, 2 RC non-ECCS welds, 2 Outboard Isolation RWCU welds, and 4 RWCU welds inside containment. Selecting from the ECCS and Outboard Isolation welds, as required by BWRVIP-75-A, welds 2B31-1RCM-12AK-3 , 2G31-1RWCU-6-D-15 , and 2G31-1RWCUM-6-D-16 were selected for examination during the 1 st Period. Note:

2G31-1RWCUM-6-D-17 will also be examined as an augmented "high-energy" line. Welds 2B31-1RC-12AR-H-5 and 2B31-1RC-12AR-J-5 will be examined during the 3 rd Period. Therefore, 6 welds or 20% of the population with hydrogen water protection will be examined during the 4 th Interval.

New Category C Scope Expansion The sample expansion criteria to be used for Category C are identical to Category A.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 11 of 40 Rev.1.0 CATEGORY D WELDS Category D welds are those made of susceptible material that have not been treated with an IGSCC remedy and in which cracks have not been reported.

New Category D Examination Frequency Category D welds are required to be examined at a frequency of 100% of the population every six years. For plants on two year fuel cy cles, this is 100% every three outages.

For welds that are effectively protected with HWC, the inspection interval can be increased so that the entire Category D population will be examined every 10 years, with at least 50% inspected during the first six years. See Table 7.

Category D Scope Weld 2E11-1RHRM-24A-10

Per drawing S-28482, ISI weld number 2E11-1RHRM-24A-10 was originally field weld 2FW-6419. 2FW-6419 joined 304 stainless steel (Pullman-Kellogg Spool 2E11-RHR-184) to carbon steel piping (Pullman-Kellogg Spool 2E11-RHR-184A). Spool drawing 2E11-RHR-184A indicates that the carbon steel piping was buttered in the shop per SK#92, machined, a nd then stress relieved. The butter material (not identified), most likely, would have been Inconel 82 using machine welding or Inconel 182 using stick welding. Per S-28483, 2FW-6419 had a GTAW root (Inconel 82) and was SMAW (stick welded Inconel 182) welded out.

Note: NUREG-0313 considers Inconel 82 to be resistant to stress corrosion cracking (not Inconel 182).

During the 1984 pipe replacement (see DCR 83-173) to change out the 304 SS piping to 316 NG SS, a cut was made at 2FW-6419. The Inconel butter remained and possibly a portion of the original weld remained as a "safe-end". This "safe-end" was then machined and welded to the 316NG SS (without having to perform additional stress relievi ng of the carbon steel pi pe, since the carbon steel piping was not welded on). Actual details of the cut requires the weld traveler sheet which has not been located. The replacement spool for 2E11-RHR-184 is shown on drawing S-60048. Per the Newport News Weld History Record archived on Spool 004737, Sheet 256, the weld material is .035" diameter Bare Wire ERNiCr-3 (Inconel 82). This weld history record al so indicates that there was a root repair requiring the excavation of an area and subsequent re-weldi ng. After welding, this weld underwent Induction Heat Stress Improvement (IH SI); however the IHSI process used a short active heating coil to prevent heating of the carbon steel piping and the determination that an effective stress improvement process has not been made.

This weld is not effectively protected by HWC because it is located in a stagnant line, it contains unidentified Inconel butter material, and it may not have had a successful IHSI process. Therefore, it was conservatively classified as Category D. The first examination using the Performance Demonstration Initiative (PDI) requirements was performed in Febr uary 2005 with a total coverage of 67% (no scans for axial flaws were possible) Th is weld consists of a thick elbow with the weld FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 12 of 40 Rev.1.0 tapering down to the thinner carbon steel piping.

Additionally, there is dip on the carbon steel side near the edge of the weld butter. This configuration does not meet PDI requirements for examination of dissimilar metal welds. However, if stress corrosion cracking occurs in this weld it should originate at the ID of the butter material, because the rest of the material in the weld joint (carbon steel, 316NG SS, and Inconel 82) have minimal susceptibility to stress corrosion cracking.

From the 2005 coverage plots, ther e was no coverage for scans looking for axial flaws. For scans for circumferential cracking the follo wing coverage was obtained:

45-degree shear wave - 100% of the base metal 45-degree RL - 78% of the required volume 60-degree RL - 91% of the required volume

Most importantly, the area of interest was scanned with the 45-degree RL transducer from the stainless elbow side and scanned from both sides with the 60-degree RL transducer. Therefore, while not meeting PDI requirements, an adequate technical examination was achieved and reasonable assurance of structural integrity was maintained. As a Category D weld, it will need to be re-examined in 2011, but was scheduled for 2009 to coincide with the SMART exams.

Note:

If it is determined that this weld had an effective IHSI it may be re-categorized as Category C.

Additionally, if documentation is found that shows that the weld but ter is Inconel 82, then the weld may be re-categorized as Category A.

Weld 2E11-1RHRM-24B-10

Per drawing S-28470, ISI weld number 2E11-1RHRM-24B-10 was originally field weld 2FW-5818. 2FW-5818 joined 304 stainless steel (Pullman-Kellogg Spool 2E11-RHR-169) to carbon steel piping (Pullman-Kellogg Spool 2E11-RHR-169A). Spool drawing 2E11-RHR-169A indicates that the carbon steel piping was buttered in the shop per SK#92, machined, a nd then stress relieved. The butter material (not identified), most likely, would have been Inconel 82 using machine welding or Inconel 182 using stick welding. Per S-28471, 2FW-5818 had a GTAW root (Inconel 82) and was SMAW (stick welded Inconel 182) welded out.

Note: NUREG-0313 considers Inconel 82 to be resistant to stress corrosion cracking (not Inconel 182).

During the 1984 pipe replacement (see DCR 83-173) to change out the 304 SS piping to 316 NG SS, a cut was made at 2FW-5818. The Inconel butter remained and possibly a portion of the original weld remained as a "safe-end". This "safe-end" was then machined and welded to the 316NG SS (without having to perform additional stress relievi ng of the carbon steel pipe , since the carbon steel piping was not welded on). Actual details of the cut requires the weld traveler sheet which has not been located. Per the Newport News Weld History Record archived on Spool 001762, Sheet 252, the weld material is .035" diameter Bare Wire ERNiC r-3 (Inconel 82). This we ld history record also indicates that there was a root re pair requiring the excavation of an area and subsequent re-welding.

After welding, this weld underwent Induction Heat Stress Improveme nt (IHSI); however the IHSI FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 13 of 40 Rev.1.0 process used a short active heating coil to pr event heating of the carbon steel piping and the determination that an effective stress improvement process has not been made.

This weld is not effectively protected by HWC because it is located in a stagnant line, it contains unidentified Inconel butter material, and it may not have had a successful IHSI process. Therefore, it was conservatively classified as Category D. The first examination using the Performance Demonstration Initiative (PDI) requirements was performed in Febr uary 2005 with a total coverage of 67% (no scans for axial flaws were possible) Th is weld consists of a thick elbow with the weld tapering down to the thinner carbon steel piping.

Additionally, there is dip on the carbon steel side near the edge of the weld butter. This configuration does not meet PDI requirements for examination of dissimilar metal welds. However, if stress corrosion cracking occurs in this weld it should originate at the ID of the butter material, because the rest of the material in the weld joint (carbon steel, 316NG SS, and Inconel 82) have minimal susceptibility to stress corrosion cracking.

From the 2005 coverage plots, ther e was no coverage for scans looking for axial flaws. For scans for circumferential cracking the follo wing coverage was obtained:

45-degree shear wave - 100% of the base metal 45-degree RL - 78% of the required volume 60-degree RL - 91% of the required volume

Most importantly, the area of interest was scanned with the 45-degree RL transducer from the stainless elbow side and scanned from both sides with the 60-degree RL transducer. Therefore, while not meeting PDI requirements, an adequate technical examination was achieved and reasonable assurance of structural integrity was maintained. As a Category D weld, it will need to be re-examined in 2011, but was scheduled for 2009 to coincide with the SMART exams.

Note:

If it is determined that this weld had an effective IHSI it may be re-categorized as Category C.

Additionally, if documentation is found that shows that the weld but ter is Inconel 82, then the weld may be re-categorized as Category A.

Weld 2E11-1RHRM-20-3

Per drawing S-28478, ISI weld number 2E11-1RHRM-20-3 was originally field weld 2FW-6219. 2FW-6219 joined 304 stainless steel (Pullman-Kellogg Spool 2E11-RHR-179) to carbon steel piping (Pullman-Kellogg Spool 2E11-RHR-179A). Spool drawing 2E11-RHR-179A indicates that the carbon steel piping was buttered in the shop per SK#93, machined, a nd then stress relieved. The butter material (not identified), most likely, would have been Inconel 82 using machine welding or Inconel 182 using stick welding. Per S-28479, 2FW-6219 had a GTAW root (Inconel 82) and was SMAW (stick welded Inconel 182) welded out.

Note: NUREG-0313 considers Inconel 82 to be resistant to stress corrosion cracking (not Inconel 182).

During the 1984 pipe replacement (see DCR 83-173) to change out the 304 SS piping to 316 NG SS, a cut was made at 2FW-6219. The Inconel butter remained and possibly a portion of the original FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 14 of 40 Rev.1.0 weld remained as a "safe-end". This "safe-end" was then machined and welded to the 316NG SS (without having to perform additional stress relievi ng of the carbon steel pipe , since the carbon steel piping was not welded on). Actual details of the cut requires the weld traveler sheet which has not been located. The replacement spool for 2E11-RHR-184 is shown on drawing S-60048. Per the Newport News Weld History Record archived on Spool 004762, Sheet 127, the weld material is .035" diameter Bare Wire ERNiCr-3 (Inconel 82). This weld history record al so indicates that there was a root repair requiring the excavation of areas and subsequent re-welding. After welding, this weld underwent Induction Heat Stress Improvement (IH SI); however the IHSI process used a short active heating coil to prevent heating of the carbon steel piping and the determination that an effective stress improvement process has not been made.

This weld is not effectively protected by HWC because it is located in a stagnant line, it contains unidentified Inconel butter material, and it may not have had a successful IHSI process. Therefore, it was conservatively classified as Category D. The first examination using the Performance Demonstration Initiative (PDI) requirements was performed in February 2005 and 100% coverage was obtained. As a Category D weld, it will need to be re-examined in 2011, but was scheduled for 2009 to coincide with the SMART exams.

Note: If it is determined that this weld had an effective IHSI it may be re-categorized as Category C. Additionally, if documentation is found that shows that the weld but ter is Inconel 82, then the weld may be re-categorized as Category A.

Weld 2B21-1FW-12AA-8 This Inconel weld joins a carbon steel pipe to a In conel extension piece.

On the Inconel side of the weld, there is a weld overlay which extends up to the edge of the weld. During the 3 rd Interval examination was from both sides as s hown in Figure 1. However, during the 4 th Interval, the examination through the overlay has not been qualified per the Performance Demonstration Initiative and the taper on the carbon steel side will limit coverage. This weld had a mechanical stress improvement process (MSIP) performed on it in 1994. However, in the Flaw Tolerance Evaluation for this weld performed by Structural Integrity Associat es (SIA) as documented in their August 25, 2006 letter SIR-06-357, Rev. 0, SIA concl uded that during the weld overlay repair, because weld #8 is in close proximity to the weld overlay, the weld #8 induced residual stress may be relieved, if not completely relieved, due to the large number of elastic-plastic thermal stress cycling from the weld overlay repa ir process at weld #9. The as-w elded stresses at weld #8 could be replaced by the stress induced by the weld overlay. Therefore, it is considered conservative in the present flaw tolerance evalua tion to use the weld #8 as-welded residual stresses with an inside surface residual stress magnitude equal to the yield strength of the material. Additionally, the effects of hydrogen are probably limited in feedwater, therefore this weld has been designated as Category D.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 15 of 40 Rev.1.0 FIGURE 1

New Category D Sample Expansion NA since 100% of the population is being examined.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 16 of 40 Rev.1.0 CATEGORY E WELDS Category E welds are those welds that have been overlayed with IGSCC resistant material.

New Category E Examination Frequency Category E welds that have received one qualified inservice examination after the post-overlay baseline examination and that have subsequently received one "qualified" examination will be examined using a 25% sample each 10-years.

Category E Scope There is one full structural Cate gory E Inconel overlay as shown in Table 8 (weld 2B21-1FW-12AA-9). While previous examinations were performed, an Appendix VIII examination was performed in 2005 to meet the prerequisite of one "qualified" examination. A re-examination will be scheduled during the 4 th Interval.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 17 of 40 Rev.1.0 TABLE 2 HATCH 2 CATEGORY A WELDS WITH EFFECTIVE HYDROGEN WATER CHEMISTRY (ASME Category B-J) 10% Sample of 67 Welds or 7 welds Each 10 Years PERIOD 1 PERIOD 2 PERI0D 3 P1 P2 P3 Category A Welds 316 NG Material Effective H 2 ? SIA Prior ECCS Note 2 3/1/1 2R13 1997 3/1/2 2R14 1998 3/2/1 2R15 2000 3/2/2 2R16 2001 3/3/1 2R17 2003 3/3/2 2R18 2005 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 1. 2B31-1RCM-12AF-1 Yes 4 YES V&S 2. 2B31-1RCM-12AF-2 Yes 4 YES

3. 2B31-1RCM-12AG-1 Yes 4 YES

4. 2B31-1RCM-12AH-1 Yes 2 YES V V 5. 2B31-1RCM-12AJ-1 Yes 4 YES

6. 2B31-1RCM-12AK-1 Yes 4 YES

7. 2B31-1RCM-12AK-2 Yes 4 YES

8. 2B31-1RCM-12BA-1 Yes 4 YES V 9. 2B31-1RCM-12BA-2 Yes 4 YES V 10. 2B31-1RCM-12BB-1 Yes 4 YES

11. 2B31-1RCM-12BC-1 Yes 2 YES

12. 2B31-1RCM-12BD-1 Yes 4 YES

13. 2B31-1RCM-12BE-1 Yes 4 YES

14. 2B31-1RCM-12BE-2 Yes 4 YES

15. 2B31-1RCM-22A-1 Yes 2 YES V V 16. 2B31-1RCM-22A-2 Yes 2 YES

17. 2B31-1RCM-22B-1 Yes 2 YES

18. 2B31-1RCM-22B-2 Yes 2 YES

19. 2B31-1RCM-28AD-1 Yes 2 NO V 20. 2B31-1RCM-28AD-2 Yes 2 NO

21. 2B31-1RCM-28AD-3 Yes 2 YES V V 22. 2B31-1RCM-28AD-4 Yes 4 YES

23. 2B31-1RCM-28AD-5 Yes 2 YES V V 24. 2B31-1RCM-28BD-1 Yes 2 NO

25. 2B31-1RCM-28BD-2 Yes 2 NO

26. 2B31-1RCM-28BD-3 Yes 2 YES V 27. 2B31-1RCM-28BD-4 Yes 4 YES

28. 2B31-1RCM-28BD-5 Yes 2 YES V V 29. 2B31-1RCM-28AS-3 Yes 4 NO

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 18 of 40 Rev.1.0 TABLE 2 HATCH 2 CATEGORY A WELDS WITH EFFECTIVE HYDROGEN WATER CHEMISTRY (ASME Category B-J) 10% Sample of 67 Welds or 7 welds Each 10 Years PERIOD 1 PERIOD 2 PERI0D 3 P1 P2 P3 Category A Welds 316 NG Material Effective H 2 ? SIA Prior ECCS Note 2 3/1/1 2R13 1997 3/1/2 2R14 1998 3/2/1 2R15 2000 3/2/2 2R16 2001 3/3/1 2R17 2003 3/3/2 2R18 2005 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 30. 2B31-1RCM-28AS-4 Yes 4 NO

31. 2B31-1RCM-28AS-5 Yes 4 NO

32. 2B31-1RCM-28AS-6 Yes 2 NO

33. 2B31-1RCM-28AS-7 Yes 4 NO

34. 2B31-1RCM-28AS-8 Yes 4 NO V 35. 2B31-1RCM-28AS-9 Yes 2 NO V&S 36. 2B31-1RCM-28AS-9BC-2 Yes 4 NO 37. 2B31-1RCM-28AS-9BC-4 Yes 4 NO 38. 2B31-1RCM-28AS-10 Yes 2 NO V 39. 2B31-1RCM-28BS-3 Yes 4 NO

40. 2B31-1RCM-28BS-4 Yes 4 NO

41. 2B31-1RCM-28BS-5 Yes 4 NO

42. 2B31-1RCM-28BS-6 Yes 4 NO

43. 2B31-1RCM-28BS-7 Yes 2 NO

44. 2B31-1RCM-28BS-8 Yes 2 NO

45. 2B31-1RCM-28BS-8BC-2 Yes 4 NO 46. 2B31-1RCM-28BS-8BC-4 Yes 4 NO 47. 2B31-1RCM-28BS-9 Yes 2 NO

48. 2E11-1RHRM-20RS-1 Yes 4 NO

49. 2E11-1RHRM-20RS-1BC-1 Yes 4 NO 50. 2G31-1RWCUM-6-D-1 Yes 4 NO V 51. 2G31-1RWCUM-6-D-2 Yes 4 NO

52. 2G31-1RWCUM-6-D-3 Yes 4 NO

53. 2G31-1RWCUM-6-D-4 Yes 4 NO

54. 2G31-1RWCUM-6-D-5 Yes 4 NO

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 19 of 40 Rev.1.0 TABLE 2 HATCH 2 CATEGORY A WELDS WITH EFFECTIVE HYDROGEN WATER CHEMISTRY (ASME Category B-J) 10% Sample of 67 Welds or 7 welds Each 10 Years PERIOD 1 PERIOD 2 PERI0D 3 P1 P2 P3 Category A Welds 316 NG Material Effective H 2 ? SIA Prior ECCS Note 2 3/1/1 2R13 1997 3/1/2 2R14 1998 3/2/1 2R15 2000 3/2/2 2R16 2001 3/3/1 2R17 2003 3/3/2 2R18 2005 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 55. 2G31-1RWCUM-6-D-8 Yes 4 NO V&S 56. 2G31-1RWCUM-6-D-9 Yes 4 NO

57. 2G31-1RWCUM-6-D-10 Yes 4 NO

58. 2G31-1RWCUM-6-D-11 Yes 4 NO

59. 2G31-1RWCUM-6-D-12 Yes 4 NO

60. 2G31-1RWCUM-6-D-13 Yes 4 NO

61. 2E11-1RHRM-20RS-2 No(1) 4 NO V 62. 2E11-1RHRM-24A-11 No(1) 4 YES 63. 2E11-1RHRM-24A-12 No(1) 4 YES 64. 2E11-1RHRM-24A-13 No(1,3) 4 YES V&S V 65. 2E11-1RHRM-24B-11 No(1,3) 4 YES V&S V 66. 2E11-1RHRM-24B-12 No(1) 4 YES 67. 2E11-1RHRM-24B-13 No(1) 4 YES 10% 3 rd Interval Reduced Scope Sample 10% 4th Interval Reduced Scope Sample Table 2 Notes (1) These welds do not have effective HWC becaus e of their location in stagnant lines, but they had an effective stress improvement (no deviations noted in the IHSI evaluation)

(2) None of the welds in this table are located between the drywell and the ou tboard isolation valve.

(3) Two of the welds without hydrogen protection were selected in the examination sample, even though there SIA Priority was low.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 20 of 40 Rev.1.0 TABLE 3 DISSIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT WITHOUT EFFECTIVE HYROGEN WATER CHEMISTRY (Note 1) 25% Sample of 12 Welds After Qualified Weld Examinations (3 welds) PERIOD 1 PERIOD 2 PERIOD 3 P1 P2 P3 Cat C (B-F) Crown or Taper ? E C C S 2R11 S 94 3/1/1 2R13 S 97 3/1/2 2R14 F 98 3/2/1 2R15 2000 3/2/2 2R16 S 01 3/3/1 2R17 S 03 3/3/2 2R18 S 05 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 1. 2B21-1FW-12AA-10 MSIP-94 SIA-1 No Yes BASE UT-HAT-208V0/0 UT-HAT-208V0/1 Note 3

2. 2B21-1FW-12AB-11 MSIP-94 SIA-1 No Yes BASE UT-HAT-208V0/0 UT-HAT-208V0/1 Note 3

3. 2B21-1FW-12AB-13 MSIP-94 SIA-1 No Yes BASE UT-HAT-208V0/0 UT-HAT-208V0/1 Note 3

4. 2B21-1FW-12BC-11 MSIP-94 SIA-1 No Yes BASE UT-HAT-209V0/0 UT-HAT-208V0/1 GE-UT-209/6 Note 4 V 5. 2B21-1FW-12BC-13 MSIP-94 SIA-1 No Yes BASE UT-HAT-209V0/0 UT-HAT-208V0/1 GE-UT-209/6 Note 4 V 6. 2B21-1FW-12BD-10 MSIP-94 SIA-1 No Yes BASE UT-HAT-208V0/0 UT-HAT-208V0/1 GE-UT-209/6 Note 4

7. 2B21-1FW-12BD-8 MSIP-94 SIA-1 No Yes BASE UT-HAT-208V0/0 UT-HAT-208V0/1 GE-UT-209/6 V Note 5 8. 2B31-1RC-4JP-A-1 MSIP-94 SIA-1 No No BASE UT-H-409/08 UT-H-409/10 UT-H-409/10 Note 6

9. 2B31-1RC-4JP-B-1 MSIP-94 SIA-1 No No BASE UT-H-409/08 UT-H-409/10 UT-H-409/10 Note 6 10. 2C11-1CRD-3-R-1 MSIP-94 SIA-4 No No BASE UT-H-409/8 UT-H-409/10 UT-H-409/10 V Note 7 11. 2E21-1CS-10A-21 MSIP-94 SIA-1 No Yes BASE UT-HAT-209V0/0 UT-HAT-209V0/1 UT-H-409/10 V Note 8 V 12. 2E21-1CS-10B-20 MSIP-94 SIA-1 No Yes BASE UT-HAT-209V0/0 UT-HAT-209V0/1 UT-H-409/10 V Note 9 Qualified weld exam to satisfy BWRVIP-075 pre-requisite for reduced scope 25% 3 rd Interval Reduced Scope Sample 25% 4th Interval Reduced Scope Sample (Note: All of the FW welds are SIA Priority 1; therefore, there is not a special basis for selecting any one of the welds. The two core spray welds were selected because they are in stagnant lines. Six of the 12 welds will receive Appendix VIII exams by 2009. Re-examined for cause after evaluation of previous data and found acceptable by Appendix VIII examination.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 21 of 40 Rev.1.0 Table 3 Notes

1. To have effective hydrogen water chemistry at Hatch requires a combination of noble metal addition and a reduced hydrogen injection rate. The Feedwater nozzle safe-ends (2B21) are not believed to have totally effective hydrogen water chemistry because the hydrogen is injected into the Feedwater lines and sufficient mixing may not have occurred. The Core Spray (2E21) safe-ends, the Jet Pump Instrument nozzle (2B31) safe-ends, and the CRD Return nozzle (2C11) safe-end are not protected by hydrogen water chemistry because of stagnant conditions due to the geometri cal configuration.

2. Not Used

3. Two automated examinations were performed (1994 baseline and 1997) on welds 2B21-1FW-12AA-10, 2B21-1FW-12AB-11, and 2B21-1FW-12AB-13 using a qualified procedure and personnel qualified for IGSCC detection.

4. Three automated examinations were performed (1994 baseline, 1997, and 2000) on welds 2B21-1FW-12BC-11, 2B21-1FW-12BC-13, and 2B21-1FW-12BD-10 using a qualified proc edure and personnel qualified for IGSCC detection. 2B21-1FW-12BC-11 and 2B21-1FW-12BC-13 will be re-examined in 2009. 5. Three automated examinations were performed (1994 baseline, 1997, and 2000) on weld 2B21-1FW-12BD-8 using a qualified procedure and personnel qualified for IGSCC detection. A review of the previous data indicated the need for a re-examination in 2005. The re-examination was performed in 2005. A review of the data did not indicate any basis for re-examination.

6. Three manual examinations were performed (1994 baseline, 1997, and 2000) on welds 2B31-1RC-4JP-A-1 and 2B31-1RC-4JP-B-1 using a qualified procedure and personnel qualified for IGSCC detection. A review of the data did not indicate any basis for re-examination.

7. Three examinations were performed (1994 baseline, 1997, and 2000) on weld 2C11-1CRD-3-R-1 using a qualified procedure and personnel qualified for IGSCC de tection. An Appendix VIII examination was performed in 2005 with 100% coverage. It should be noted that this weld was stress improved in 1994, but effective hydrogen water chemistry is not achieved because of the stagnant configuration.

8. Three examinations were performed (1994 automated baseline, 1997 automated, and 2000 manual) on weld 2E21-1CS-10A-21 using a qualified procedure and personnel qualified for IGSCC detection. It should be noted that this weld was stress improved in 1994, but effective hydrogen water chemistry is not achieved because of the stagnant configuration. There were some questions regarding previous examinations; however, the weld was re-examined in 2005 without issues and will be re-examined in 2015. 9. Three examinations were performed (1994 automated baseline, 1997 automated, and 2000 manual) on weld 2E21-1CS-10B-20 using a qualified procedure and personnel qualified for IGSCC detection. It should be noted that this weld was stress improved in 1994, but effective hydrogen water chemistry is not achieved because of the stagnant configur ation. In 2005 an Appendix VIII examination of this weld was performed with 100% coverage and this weld will be re-examined in 2015.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 22 of 40 Rev.1.0 TABLE 4 DISSIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT AND HYDROGEN WATER CHEMISTRY (Note 1) 10% Sample of 12 Welds After Two Qualified Weld Examinations (2 Welds) PERIOD 1 PERIOD 2 PERIOD 3 P1 P2 P3 Cat C (B-F) Welds

E C C S 2 3 2R11 S 94 3/1/1 2R13 S 97 3/1/2 2R14 F 98 3/2/1 2R15 2000 3/2/2 2R16 S 01 3/3/1 2R17 S 03 3/3/2 2R18 S 05 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 1. 2B31-1RC-12AR-F-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-HAT-209V0/0 V Note 2 2. 2B31-1RC-12AR-G-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-HAT-209V0/0 UT-HAT-209V0/1 UT-H-409/10 1997 Pickup Note 3

3. 2B31-1RC-12AR-H-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-HAT-209V0/0 GE-UT-209/6 V Note 4 V 4. 2B31-1RC-12AR-J-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-HAT-209V0/0 V Note 2 V 5. 2B31-1RC-12AR-K-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-HAT-209V0/00 UT-HAT-209V0/1 UT-H-409/10 1997 Pickup V Note 5 6. 2B31-1RC-12BR-A-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-H-810/0 + UT-H-409/7(91) - UT-HAT-209V0/1 UT-H-409/10 1997 Pickup Note 6

7. 2B31-1RC-12BR-B-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-H-810/0 + UT-H-409/7(91) - GE-UT-209/6 UT-H-409/10 V Note 7 8. 2B31-1RC-12BR-C-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-H-810/0 + UT-H-409/7(91) - GE-UT-209/6 V Note 7 FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 23 of 40 Rev.1.0 TABLE 4 DISSIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT AND HYDROGEN WATER CHEMISTRY (Note 1) 10% Sample of 12 Welds After Two Qualified Weld Examinations (2 Welds) PERIOD 1 PERIOD 2 PERIOD 3 P1 P2 P3 Cat C (B-F) Welds

E C C S 2 3 2R11 S 94 3/1/1 2R13 S 97 3/1/2 2R14 F 98 3/2/1 2R15 2000 3/2/2 2R16 S 01 3/3/1 2R17 S 03 3/3/2 2R18 S 05 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 9. 2B31-1RC-12BR-D-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-H-810/0 + UT-H-409/7(91) - UT-HAT-209V0/1 UT-H-409/10 UT-H-409/10 1997 Pickup V Note 7 10. 2B31-1RC-12BR-E-5 IHSI-86&UT Baseline SIA Priority 1 Y UT-H-409/5(89) UT-H-810/0 + UT-H-409/7(91) - GE-UT-209/6 Note 6 11. 2B31-1RC-28A-1 IHSI-86&UT Baseline SIA Priority 1 N UT-H-409/5(89) UT-H-810/0 + UT-H-409/7(91) - GE-UT-209/6 Note 6 12. 2B31-1RC-28B-1 IHSI-86&UT Baseline SIA Priority 1 N UT-H-409/5(89) UT-H-810/0 + UT-H-409/7(91) - GE-UT-209/6 Note 6 Qualified weld exam to satisfy BWRVIP-075 pre-requisite for reduced scope 10% 3 rd Interval Reduced Scope Sample 10% 4th Interval Reduced Scope Sample Dissimilar metal welds that do not meet examination criteria Re-examined for cause after evaluation of previous data and found acceptable by Appendix VIII examination.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 24 of 40 Rev.1.0 Table 4 Notes

1. Each weld had an effective IHSI stress improved in 1986 and effective hydrogen water chemistry is implemented.

2. Welds 2B31-1RC-12AR-F-5 and 2B31-1RC-12AR-J-5 have been examined twice using a qualified procedure and personnel qualified for IGSCC detection. A manual examination was performed in 1989 and an automated examination was performed in 1994. These welds have a CE repair history and have an ECCS function. After evaluation of the data it was determined that with the repair history and some issues with the data, an additional automated examination would be performed in 2005. These welds were Appendix VIII examined in 2005 with no issues. 2B31-1RC-12AR-J-5 will be re-examined in 2015.

3. Weld 2B31-1RC-12AR-G-5 has been examined three times using a qualified procedure and personnel qualified for IGSCC detection. A manual examination was performed in 1989. Automated examinations were performed in 1994 and 1997. The exam shown in 2000 is a manual pickup to complete the 1997 exam. This weld does not have a CE repair history. After evaluation of the data, with a 1994 and 1997 automated examination and with no repair history, this weld was not selected for future examinations.

4. Weld 2B31-1RC-12AR-H-5 has been examined three times using a qualified procedure and personnel qualified for IGSCC detection. A manual examination was performed in 1989 and automated examinations were performed in 1994 and 2000. This weld has a CE repair history and has an ECCS function. After evaluation of the data it was determined that with the repair history and NDE data issues, an automated examination would be performed in 2005. This weld was Appendix VIII examined in 2005 with no issues. It will be re-examined in 2015.

5. Weld 2B31-1RC-12AR-K-5 has been examined three times using a qualified procedure and personnel qualified for IGSCC detection. A manual examination was performed in 1989. Automated examinations were performed in 1994 and 1997. The exam shown in 2000 is a manual pickup to complete the 1997 exam. This weld does not have a CE repair history. After evaluation of the data it was determined that due to issues with the NDE data, an automated examination would be performed in 2005. This weld was Appendix VIII examined in 2005 with no issues.

6. Welds 2B31-1RC-12BR-A-5 , 2B31-1RC-12BR-E-5, 2B31-1RC-28A-1, and 2B31-1RC-28B-1 have been examined three times using a qualified procedure and personnel qualified for IGSCC detection. A manual examination was performed in 1989. PSCAN automated examinations were performed in 1991 on all the welds. Weld A-5 had a GE automated examination in 1997 and the other welds had a GE automated examination in 2000. These welds do not have a CE repair history. There are no issues with the data and there is no repair history; therefore, these welds were not selected for future examinations

7. Welds 2B31-1RC-12BR-B-5, 2B31-1RC-12BR-C-5 , and 2B31-1RC-12AR-D-5 have been examined three times using a qualified procedure and personnel qualified for IGSCC detection. A manual examination was performed in 1989. PSCAN automated examinations were performed in 1991 on all the welds. Weld D-5 had a GE automated examination in 1997 and the other welds had a GE automated examination in 2000. These welds have a CE repair history and have an ECCS function. There were no issues with the data; however, because of the repairs they were selected for an additional examination in 2005. This weld was A ppendix VIII examined in 2005 with no issues..

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 25 of 40 Rev.1.0 TABLE 5 SIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT WITHOUT EFFECTIVE HYROGEN HWC (Note 1) 25% Sample of 5 Welds After Two Qualified Weld Examinations (2 Welds)

PERIOD 1 PERIOD 2 PERIOD 3 P1 P2 P3 Category C (B-J) Welds E C C S 1 2 3 2R11 S 94 3/1/1 2R13 S 97 3/1/2 2R14 F 98 3/2/1 2R15 2000 3/2/2 2R16 S 01 3/3/1 2R17 S 03 3/3/2 2R18 S 05 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 1. 2B21-1FW-12AB-12 MSIP-1994 SIA Priority 1 Y NA NA BASE UT-HAT-208V0/0 UT-HAT-208V0/1 Note 2

2. 2B21-1FW-12BC-12 MSIP-1994 SIA Priority 4 Y NA NA BASE UT-HAT-208V0/0 UT-HAT-208V0/1 GE-UT-230/2 Note 2 V 3. 2B21-1FW-12BD-9 MSIP-1994 SIA Priority 4 Y NA NA BASE UT-HAT-208V0/0 UT-HAT-208V0/1 UT-H-402/1 Note 2 V 4. 2B31-1RC-4JP-A-2 MSIP-1994 N NA NA BASE UT-H-400/12 UT-H-400/16 Note 3

5. 2B31-1RC-4JP-B-2 MSIP-1994 N NA NA BASE UT-H-400/12 UT-H-400/16 Note 3 Qualified weld exam to satisfy BWRVIP-075 pre-requisite for reduced scope 25% 3 rd Interval Reduced Scope Sample 25% 4th Interval Reduced Scope Sample (moved exams to a higher SIA Priority)

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 26 of 40 Rev.1.0 Table 5 Notes

1. Each weld was stress improved with MSIP in 1 994. MSIP is considered to be an effective stress improvement process. Effective hydrogen water chemistry at Hatch is implemented using noble metal addition and a reduced hydrogen injection rate. The Feedwater nozzle safe-ends (2B21) are not believed to have totally effective hydrogen water chemistry because the hydrogen is injected into the Feedwater lines and sufficient mixing may not have occurred. The Jet Pump Instrument nozzle (2B31) sa fe-ends are not protected by hydrogen water chemistry because of stagnant conditions due to the geometrical configuration. With a stagnant condition it is unlikely that the welds were coated with noble metal.

2. Two examinations were performed using NDE personnel qualified for IGSCC detection. These examinations were a 1994 automated base line using GE procedure UT-HAT-208V0/0 and a 1997 automated inservice examination using GE procedure UT-HAT-208V0/1. As discussed in the "Qualified Examination" se ction of this report UT-HAT-208V0/0 and UT-HAT-208V0/1 both utilized the same essentia l variables as were later used for PDI demonstrations (on dissimilar metal welds). Therefore, these examinations met the BWRVIP-075 requirement for qualified examinations.

In addition, welds 2B21-1FW-12BC-12 and 2B21-1FW-12BD-9 were re-examined in 2000 us ing a qualified proce dure and personnel qualified for IGSCC detection. These 2000 examinations were performed after the March 1, 1996 (transition letter) and about the time Appendix VIII stainless was implemented for stainless steel piping (5/22/2000). Welds 2B21-1FW-12BC-12 and 2B21-1FW-12BD-9 have an ECCS function (HPCI injection path) and their re-examination satisfies the 25% sample rate during the 3 rd 10-year interval. They will be re-examined in 2015.

3. Two examinations were performed using SNC manual examination procedures and NDE personnel qualified for IGSCC detection. These examinations were a 1994 manual baseline using procedure UT-H-400/12 (pre-1996 transiti on letter) and a 1997 inservice examination using procedure UT-H-400/16 (post-1996 tran sition letter). While UT-H-400/12 was developed and used prior to the 1996 transition letter, it used similar techniques to those used later in UT-H-400/16, and therefor e it is also considered to m eet the intent of the BWRVIP-075 requirements for a "qualified' examination.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 27 of 40 Rev.1.0 TABLE 6 SIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT AND HYDROGEN WATER CHEMISTRY (Note 1) 10% Sample of 18 Welds After Two Qualified Weld Examinations (2 Welds) PERIOD 1 PERIOD 2 PERIOD 3 P1 P2 P3 Category C (B-J) Welds

E C C S 1 2 3 2R11 S 94 3/1/1 2R13 S 97 3/1/2 2R14 F 98 3/2/1 2R15 S 00 3/2/2 2R16 S 01 3/3/1 2R17 S 03 3/3/2 2R18 S 05 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 1. 2B31-1RCM-12AF-3 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - GE-UT-230/2 Note 2

2. 2B31-1RCM-12AG-2 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - UT-HAT-208V0/1 Note 3

3. 2B31-1RCM-12AH-2 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - GE-UT-230/2 Note 2

4. 2B31-1RCM-12AJ-2 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - GE-UT-230/2 Note 2

5. 2B31-1RCM-12AK-3 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - UT-HAT-208V0/1 GE-UT-230/2 Note 3 V 6. 2B31-1RCM-12BA-3 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - UT-HAT-208V0/1 Note 3

7. 2B31-1RCM-12BB-2 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - GE-UT-230/2 Note 2

8. 2B31-1RCM-12BC-2 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - GE-UT-230/2 Note 2

9. 2B31-1RCM-12BD-2 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - UT-HAT-208V0 GE-UT-230/2 Note 3 V 10. 2B31-1RCM-12BE-3 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - GE-UT-230/2 Note 2 FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 28 of 40 Rev.1.0 TABLE 6 SIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT AND HYDROGEN WATER CHEMISTRY (Note 1) 10% Sample of 18 Welds After Two Qualified Weld Examinations (2 Welds) PERIOD 1 PERIOD 2 PERIOD 3 P1 P2 P3 Category C (B-J) Welds E C C S 1 2 3 2R11 S 94 3/1/1 2R13 S 97 3/1/2 2R14 F 98 3/2/1 2R15 S 00 3/2/2 2R16 S 01 3/3/1 2R17 S 03 3/3/2 2R18 S 05 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 11. 2B31-1RCM-28AS-2 IHSI-84 (1) SIA Priority 4 N UT-H-401/6 (88) - - GE-UT-230/2 Note 2 12. 2B31-1RCM-28BS-2 IHSI-84 (1) SIA Priority 4 N UT-H-401/6 (88) - - GE-UT-230/2 Note 2 13. 2G31-1RWCUM-6-D-6 IHSI-84 (1) SIA Priority 2 N UT-H-401/6 (88) - - UT-H-400/16 Note 4 14. 2G31-1RWCUM-6-D-7 IHSI-84 (1) SIA Priority 2 N UT-H-401/6 (88)

UT-H-400/16 Note 4 15. 2G31-1RWCUM-6-D-14 IHSI-84 (1) SIA Priority 2 N UT-H-401/6 (88) - - UT-H-402/1 Note 4 16. 2G31-1RWCUM-6-D-15 IHSI-84 (1) SIA Priority 4 Y UT-H-401/6 (88) - - UT-H-402/1 Note 4 V V 17. 2G31-1RWCUM-6-D-16 IHSI-84 (1) SIA Priority 2 Y UT-H-401/6 (88) - - UT-H-402/1 Note 4 V V 18. 2G31-1RWCU-6-D-17 IHSI-84 (1) SIA Priority 2 N UT-H-400/7 (88) - - UT-H-402/1 Note 4 V V Qualified weld exam to satisfy BWRVIP-075 pre-requisite for reduced scope 10% 3 rd Interval Reduced Scope Sample 10% 4th Interval Reduced Scope Sample High Energy - Examine 100%

(1) Baseline examination performed in 1984 after IHSI using UT-H-401/3, Dev. 1.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 29 of 40 Rev.1.0 Table 6 Notes

1. Each weld had an effective IHSI stress improved in 1986 and effective hydrogen water chemistry is implemented.

2. Two examinations were performed using NDE personnel qualified for IGSCC detection. These examinations were a 1988 inservice examination using SNC manual procedure UT-H-401/6 (pre-1996 transition letter) and a 2000 automated inservice examination using GE procedure GE-UT-230/2 (post-1996 transition letter). While UT-H

-401/6 was developed and used prio r to the 1996 transition letter, it used similar techniques to those used in post-1996 implementation lett er IGSCC detection procedures , and therefore it is also considered to meet the intent of the BWRVIP-075 requirements for a "qualified' examination. The 2000 automated examinations were performed after the March 1, 1996 transition letter and about the time Appendix VIII was implemented for stainless steel piping (5/22/2000) and also meet the BWRVIP-075 requirements for a "qualified" examination.

3. Two examinations were performed using NDE personnel qualified for IGSCC detection. These examinations were a 1988 inservice examination using SNC manual procedure UT-H-401/6 (pre-1996 transition letter) and a 1997 automated inservice examination using GE procedure UT-HAT-208V0/1(post-1996 transition letter). While UT-H-401/6 was developed and used prior to the 1996 transition letter, it used similar techniques to those used in post-1996 implementation letter IGSCC detection procedures , and theref ore it is also considered to m eet the intent of the BWRVIP-075 requirements for a "qualified' examination. The 1997 post-1996 transition letter examinations using UT-HAT-208V0/1 utilized the same essential variables as were later used fo r PDI demonstrations (on dissimilar metal welds). Therefore, these examinations met the BWRVIP-075 requirement for two qualified examinations.

Additionally, welds 2B31-1RCM-12AK-3 and 2B31-1 RCM-12BD-2 (which have an ECCS function) were re-examined in 2000 using GE automated procedure GE-UT-230/2. These 2000 automated examinations were performed after the March 1, 1996 transition letter and about the time Appendix VIII was implemented for stainless steel piping (5/22/2000). These two examinations satisfied the 10% examination requirement.

4. These six Category C welds join replacement piping made from resistant material (316NG) to original RWCU valves (or the containment penetration in one case). Two examinations were performed on each weld using NDE personnel qualified for IGSCC detection. In 1988 an inservice examination using SNC manual procedure UT-H-401/6 (pre-1996 transition letter) was performed on all six welds. While UT-H-401/6 was developed and used prior to the 1996 tran sition letter, it used similar techniques to those used in post-1996 implementation letter IGSCC detection procedures , and therefore it is also considered to meet the intent of the BWRVIP-075 requirements for a "qualified' examination.

5. 2G31-1RWCUM-6-D-6&7 were re-examined in 1997 using SNC manual procedure UT-H-400/16. These examinations were performed after the Marc h 1, 1996 transition letter and are considered as "qualified" examinations. In 2000, an inservice examination was performed on the remaining four welds using SNC manual procedure UT-H-402/1. These 2000 automated examinations were performed after the March 1, 1996 transition letter and about the time Appendix VIII was implemented for stainless steel piping (5/22/2000).

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 30 of 40 Rev.1.0 TABLE 7 CATEGORY D WELDS Cat D Welds (Limited Hydrogen Protection)

C R O W N S I A E C C S 1 2 3 2R11 S 94 3/1/1 2R13 S 97 3/1/2 2R14 F 98 3/2/1 2R15 2000 3/2/2 2R16 S 01 3/3/1 2R17 S 03 3/3/2 2R18 S 05 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2015 1. 2E11-1RHRM-20RS-3 IHSI-84 (1) 1 N UT-H-401/6 (88) UT-H-409/5 (89) - UT-H-409/10 V V V 2. 2E11-1RHRM-24A-10 IHSI-84 (1) Y 1 Y UT-H-401/6 (88) UT-H-409/5 (89) - UT-H-409/10 V V V 3. 2E11-1RHRM-24B-10 IHSI-84 (1) Y 1 Y UT-H-401/6 (88) UT-H-409/5 (89) UT-H-409/10 V V V 4. 2B21-1FW-12AA-8 MSIP-94 SIA-1 Y UT-HAT-208V0/1 V V FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 31 of 40 Rev.1.0 TABLE 8 CATEGORY E WELDS Category E Welds Description 2/1 2/2 2/3 3/1 3/1 3/3 4/1/1 2R19 2007 4/1/2 2R20 2009 4/2/1 2R21 2011 4/3/1 2R22 2013 4/3/2 2R23 2013 2B21-1FW-12AA-9 SAFE-END EXTENSION TO SAFE-END OVERLAY 86 89 91 92 94 1997 using UT-HAT-212V0 UT-H-408 2005 (App. VIII) V FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 32 of 40 Rev.1.0 APPENDIX A DETERMINATION OF "QUALIFIED" EXAMINATIONS Per BWRVIP-075, the training and qualification of examiners and procedures for application to BWR stainless steel piping welds was established in the mid 1980s and governed under the IGSCC/NDE Coordination Pl an, also referred to as the Three Party Agreement. The IGSCC/NDE Coordination Plan was jointly de veloped and approved by the NRC, EPRI, and the BWR Owner's Group on IGSCC Research and was documented in GL88-01 and NUREG-0313, Rev

2. GL 88-01 states in part:"- the detailed procedure, equipment and examina tion personnel shall be qualified by a formal program approved by the NRC such as that being conducted in accordance with the NDE Coordination Plan agreed upon by NRC, EPRI and the BWROG-". The most significant improvements in inspection methods were well implemented by 1988, and the examinations performed since that time (and in accordance with GL 88-01) are considered very reliable. Per BWRVIP-075, personnel and procedures used for the examination of piping must have been and will continue to be in accordance with one of the following two documents.

o The program identified in William T. Russell, "Transition From the IGSCC Qualification Program to the Performance Demonstration Initiative Program," letter

to K. P. Donovan, March 1, 1996.

o Performance Demonstration Initiative (PDI), Performance Description, Revision 1, Change 1, December 1996 (or later).

For HNP-2, the timing of the implementation of these improved inspection methods is contingent on the type of weld. Dependent upon the type of weld (dissimilar or similar), the improvements in inspection methods may have been adopted prior to the William T. Russell 1996 letter. These weld types are addressed below.

Dissimilar Metal Welds - These welds have historically been difficult to examine for IGSCC detection due to their configuration. Because of th is difficulty, GE issued SIL-455 which incorporated L-wave techniques and other improvements for the detection of IGSCC. Since the issuance of SIL-455, othe r issues have been identified concerning the weld crown configuration. It is the posit ion of M&IS Level III personnel, that when NDE personnel qualified for IGSCC detection used NDE procedures incorporating SIL-455, that the examinations were qualified provided that the existing weld crown contours would now be acceptable for Appendix VIII examinations. In general, those examinations performed on welds that would not meet Appendix VIII requirements for weld crowns would not be considered as "qualified examinations". Acceptable procedures are:

a. GE procedure UT-HAT-208 Version 0, Revision 0 and up, "Procedure for Automated Ultrasonic Examination of Similar and Dissimilar Metal Piping Welds" used the same essential variables that were used for Appendix VIII qualification.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 33 of 40 Rev.1.0 This procedure was used in 1994 and 1997 and meets the BWRVIP-075 intent for a "qualified" procedure.

b. GE procedure UT-HAT-209 Version 0, "Procedure for Automated Ultrasonic Examination of Dissimilar Metal Piping We lds" used the "improved" refracted L wave inspection techniques per GE SIL 455 and examination personnel were qualified for IGSCC detection. This pr ocedure was used in 1994 and 1997 and meets the BWRVIP-075 intent fo r a "qualified" procedure.

c. GE procedure GE-UT-209 Revision 6, "P rocedure for Automated Ultrasonic Examination of Dissimilar Metal Piping Welds" used the same essential variables that were used for Appendix VIII qualification. This procedure was used in 2000 and meets the BWRVIP-075 intent for a "qualified" procedure.

d. SNC Procedure UT-H-409, Revisions 5 and up used the "improved" refracted L wave inspection techniques per GE SIL 455, Revision 1 and examination personnel

were qualified for IGSCC detection. Versi ons of this procedure were used in 1989, 1994, 1997, and 2000 and meets the BWRVIP-075 intent for a "qualified"

procedure.

e. SNC Procedure UT-H-810/0 used the P-SCAN and used the "improved" refracted L wave inspection techniques per GE SIL 455, Revision 1 and examination personnel

were qualified for IGSCC detection. This procedure was used in 1991 and meets the BWRVIP-075 intent for a "qualified" procedure.

Similar Metal Welds - For similar metal welds, it is the position for HNP-2 that the NDE techniques (personnel and procedures) used from 1988 until the present are considered acceptable for the detection of IG SCC. Therefore, those welds receiving an examination by IGSCC qualified personnel using one of the below listed procedures has received a "qualified" examination.

a. GE procedure UT-HAT-208 Version 0, Revision 0 and up, "Procedure for Automated Ultrasonic Examination of Similar and Dissimilar Metal Piping Welds" used the same essential variables that were used for Appendix VIII qualification. This procedure was used in 1994 and 1997 and meets the BWRVIP-075 intent for a

"qualified" procedure.

b. GE procedure GE-UT-230/2. This procedure was used in 2000 after the issuance of the "Transition From the IGSCC Qualification Program to the Performance Demonstration Initiative Program," 1996 letter and thus meets the BWRVIP-075 intent for a "qualified" procedure.

c. SNC procedure UT-H-402/1. This procedure was used in 2000 after the issuance of the "Transition From the IGSCC Qualification Program to the Performance Demonstration Initiative Program," 1996 letter and thus meets the BWRVIP-075 intent for a "qualified" procedure.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 34 of 40 Rev.1.0

d. SNC procedure UT-H-400/16. This procedur e was used in 1997 after the issuance of the "Transition From the IGSCC Qualification Program to the Performance Demonstration Initiative Program," 1996 letter and thus meets the BWRVIP-075 intent for a "qualified" procedure.

e. SNC procedure UT-H-400/12. This procedure was used in 1994 before the issuance of the "Transition From the IGSCC Qualification Program to the Performance Demonstration Initiative Program," 1996 letter. However, the techniques are similar to that for Revision 16; therefore, it meets the BWRVIP-075 intent for a "qualified" procedure.

f. SNC procedure UT-H-401/8. This procedure was used in 1988 before the issuance of the "Transition From the IGSCC Qualification Program to the Performance Demonstration Initiative Program," 1996 letter. However, the techniques are similar to that for current revisions; therefore, it meets the BWRVIP-075 intent for a "qualified" procedure.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 35 of 40 Rev.1.0 APPENDIX B DETERMINATION OF "EFFECTIVE" HYDROGEN WATER (HWC)

Per BWRVIP-075, plants that operate with effective HWC may further reduce their inspection frequency. The definition of ef fective HWC is provided in Section 3.6 of BWRVIP-075. BWRVIP states that "licensees that take credit for HWC should verify and validate that an effective HWC program, in accordance with the staff-approved BWRVIP-62 guidelines, has been achieved. BWRVIP

-62, titled "Technical Basis for Inspection Relief for BWR Internal Components with H ydrogen Injection", provides the technical bases and criteria for an effective HWC/NMCA program to mitigate IGSCC of BWR internals and to demonstrate that inspection relief is justified for BWR internals. HNP-2 will follow the guidance in BWRVIP-62 for an effective HWC program in regards to piping and vessel internals inspection relief.2 HNP-2 has overall effective hydrogen water chemistry (HWC) as determined by the measured ECP value at the bottom of the RPV. To achieve effective HWC, HNP-2 periodically injects noble me tal and continuously injects a reduced level of hydrogen.

Issue By EPRI letter dated April 27, 2006 from Robin Dyle and Tom Mulford, the BWRVIP issued instructions to the i ndustry that generic application of inspection relief for HWC or NMCA should not be used until the NRC SE on BWRVIP-62 is issue

d. The letter also indicated that the application of BWRVIP

-62 to BWRVIP-75-A inspections is not generically authorized, but plant-specific application can be pur sued with the NRC as noted on Footnote 1 of Table 3-1 or in Section 3.6 of BWRVIP-75-A.

Response HNP is using specific relief.

Evaluation

By letter dated June 23, 2000, SNC submitted a request to adopt the guidance contained in the October 1999 version of BWRVIP-75 for weld examination sample determination and scope expansion criteria, beginning with the Unit 1 Fall 2000 outage. By letter dated October 10, 2000 the NRC issued a letter encl osing the HNP Safety Evaluation (SE). Within the HNP SE the NRC indicated that the NRC staff had reviewed the BWRVIP-75 report (and issued its generic Safety Evaluation (SE) in a letter dated September 15, 2000) and found VIP-75 acceptable except for certain open items. One of these open items dealt with defining effective hydrogen water chemistry (HWC). Section 3.6 of BWRVIP-75 stated, "for the purposes of this report, effective HWC (including NMCA) is any combination of electrochemical corrosion potential(ECP) and percent availability that results in a factor of improvement of 3, or higher on crack growth as defined using the means described in BWRVIP-62." To address the NRC questions SNC provided justification in the form of an attachment to the June 23, 2000 letter. It stated:

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 36 of 40 Rev.1.0 The Chemistry Monitoring Program at Pl ant Hatch provides guidance for operating both Units in accordance with the EPRI BWR Water Chemistry guidelines. Water chemistry control parameters are monitored and action levels are used by plant staff members to correct water chemistry conditions and evaluated those conditions, as

required.

Hatch Unit 2 has been operating with HWC since September of 1991. From May 1994 to March 2000 (Cycles 12, 13, 14, &15), Unit 2 has operated under moderate HWC with hydrogen injection at 35 - 55 SCFM, conductivity measured in the 0.08 to 0.14 S/cm range, and Electro-Chemical Potential (ECP) measurements in the -400 to -450 SHE range. HWC availability has been maintained at > 80% since the initial implementation. At the shutdown of Cycle 15 (Spring 2000), NobleChem (NMCA) was added to Unit 2. The NobleChem addition was implemented with both reactor coolant system (RCS) recirculation pumps in operation to achieve as much distribution to the RCS piping as possible. During Cycl e 16 (current cycle), hydrogen injection has been maintained at 6 to 8 SCFM and ECP is measured at -450 to -480 SHE.

Within the HNP SE, the NRC concluded that SNC's response to the open item in the BWRVIP-75 SE was acceptable. Therefore specific relief regarding the HWC/NMCA program at Hatch was granted.

Footnote 1 of Table 3-1 of BWRVIP-75-A states, "For the examination sample percentages that are less than required by ASME Section XI, a licensee will need to pursue an alternative to 10 CFR 50.55a requirements for category B-J and B-F welds pursuant to 10 CFR 50.55a(a)(3)(i).

Pursuant to 10 CFR 50.55a(a)(3)(i), SNC submitted alternative RR-39 for the 3 rd Interval and approval was granted by the NRC on January 7, 2005. For the 4 th Interval SNC submitted ISI-ALT-3 which was approved by the NRC on December 22, 2005.

Current Implementation of HWC and NMCA ISI-ALT-3 was submitted to continue use of the guidance contained in the Electric Power Research Institute (EPRI) proprietary report TR-113932, "BWR Ve ssel and lnternals Project, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (BWRVIP-75)," dated October 1999, as revi sed by the Nuclear Regulatory Commission (NRC) staff's final Safety Evaluation dated May 14, 2002, in lieu of the licensee's commitments to Generic Letter 88-01 a nd NUREG-0313, Revision 2. The NRC staff concluded that the licensee's proposed alternative provides an acceptable level of quality and safety. The NRC staff authorized the proposed alternative fo r the fourth 10-year inservice inspection interval. Dennis Rickertson was requested to compare the HWC/NMCA program at Hatch versus the NRC Open Item 3.8 in the NRC's SE and subsequently supplied the following information.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 37 of 40 Rev.1.0 Information Summary To provide verification and validation of the effective HWC program at Hatch - May 3, 2006

References:

NRC SE for BWRVIP-75-A and the NRC BWRVIP-75-A report NRC Letter

Subject:

SE for BWRVIP-62 January 30, 2001

BWRVIP letter to the NRC

Subject:

Supplementary Information on Implementation of BWRVIP-62 December 17, 2004

Hatch IGSCC Mitigation History and Strategy

Hydrogen Water Chemistry was initiated to mitigate IGSCC of Recirculation System piping (Unit 1 Sept 1987, Unit 2 Sept 1991). From 1992 to 1995, hydrogen injection flow rates were gradually increased from 22 SCFM to 50 SCFM to mitigate IG SCC of reactor vessel internal lower plenum area. From 1995 to 1999, Hatch operated with moderate hydrogen injection rates of 45 to 55 SCFM. NMCA was applied to Unit 1 at the End of Cycle (EOC) 18 in March of 1999 and Unit 2 at the EOC 15 in March of 2000. For the operating cycle after NMCA, the target hydrogen injection flow rates were set at 10 SCFM (0.26 ppm) in the feedwater. From 1998 to 2002, SNC participated

in the Japanese Owner's Group (JOG) program which evaluated HNP-2 reactor vessel lower head region for protection via extensive ECP monitoring.

Current HNP IGSCC Mitigation Strategy is to contin ue to use NMCA with hydrogen injection at 10 SCFM. The primary methods of monitoring hydrogen water chemistry effectiveness of mitigating IGSCC are ECP monitoring and Noble Metal durability monitoring. Also the feedwater hydrogen injection flow rate is monitored and the Molar Ratio of Hydrogen to Oxidants is calculated using the BWRVIA computer model. These two methods are secondary methods of monitoring HWC effectiveness. At a hydrogen injection flowrate of 10 SCFM, ECP values are normally -450 to -490 mV (SHE) at the Bottom Head Drain Line, Recirculating System piping, and MMS.

Also with the feedwater hydrogen injection flow rate of 10 SFFM, the results of the BWRVIA model indicate Molar Ratios greater than 3 in the recirculation piping and reactor internals (except the mixing plenum) locations. A Molar Ratio greater th an 3 indicates ECP values are in the - 400 mV range. The BWRVIA model indicates that at a Feedwater hydrogen injection rate of 10 SCFM the Molar Ratio in the Recirculating System piping is greater than 10. The NRC SE for BWRVIP-62 (letter of Jan 30, 2001) indicates: for an acceptable NMCA program the Molar Ratio should be 4 and above, and that HWC % availability should be > 90%. Supplementary information was provided to the NRC (BWRVIP letter of December 17, 2004) indicating that a molar ratio of > 3 is sufficient to mitigate IGSCC (ECP < -230 mV).

Results of the Hatch HWC Percent Availability calcul ations indicate that for Unit 1 since November 1997, the percent availability has been greater than 80 %. For Unit 2, since April 1997, the percent availability has been greater than 80 %. Both Units have HWC percent availability > 90 % after the NMCA applications: Unit 1 1999 EOC18, and Unit 2 2000 EOC15.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 38 of 40 Rev.1.0 Unit 1 Unit 2 Cycle  % HWC Availability Cycle  % HWC Availability 18 98.2 14 93 19 91.1 15 84.5 20 94 16 97.2 21 98 17 96.9 22 97.6 18 98.8 23 86.5 (current cycle) 19 98.14 (current cycle)

Water Chemistry and durability monitoring results will be reviewed periodically with GE to determine when NMCA should be re-applied.

Locations Where Effective HWC/NMCA is Not Credited It should be noted that while HNP-1 has effective HWC, individual welds may or may not have effective HWC because of their location.

To have effective HWC at each weld of interest, the noble metal must have plated out on each weld to provide protection for the weld, and the water chemistry at each weld must have sufficient hydrogen to sufficiently lower the oxygen content. For HNP-1, all welds are considered to have effective HWC except for the following.

o Welds located in stagnant areas, including:

Core Spray nozzles - carbon steel pipe to stainless safe-end extension (1 dissimilar metal weld per nozzle), stainle ss steel safe-end extension to stainless steel safe-end (1 similar metal weld pe r nozzle), and stainle ss steel safe-end to Inconel buttered nozzle (1 dissimilar metal weld per nozzle).

Jet Pump Instrument safe-end welds (2 nozzles with 2 welds on each nozzle).

CRD nozzle to cap weld (1 nozzle with 1 weld).

o Welds located in piping with no flow during power operation including:

RHR Suction Line - Welds downstream of the RWCU connection.

RHR Injection Lines - All welds.

The Recirculation Inlet nozzle to safe-end welds were also evaluated because they are covered by a thermal sleeve. Per drawing 2-BF-2, the thermal sleeve is open-ended on the downstream side. Therefore, flow turbulen ce inside the RPV can cause flow under the thermal sleeve and these welds are considered as protected by hydrogen water chemistry.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 39 of 40 Rev.1.0 APPENDIX C DETERMINATION OF "EFFECTIVE" STRESS IMPROVEMENT Processes used at HNP-2 were Induction Heating Stress Improvement (IHSI) and the Mechanical Stress Improvement Process (MSIP). Internal meetings were held on August 2-3, 2003 to assess compliance with the Draft A-Version of BWRVIP-075 that, "The Owner must ensure that an effective stress improvement was achieved." It was agreed that those welds receiving an MSIP treatment had an effective stress improvement; however, it was concluded that SNC had not performed sufficient actions to ensure that an effective stress improvement was achieved for those welds receiving the IHSI process. To provide this assurance, it was recommended that the NUTECH process for IHSI at Hatch be evaluated against later BWRVIP-61 recommendations for an effective stress improvement using the following criteria:

o If the NUTECH procedures met the BWRVIP-61 guidelines, then an effective IHSI was considered to have been performed.

o For those welds where the NUTECH procedure did not meet BWRVIP-61 guidance, if the NUTECH data complied with the BWRVIP-61 parameters, then an effective stress improvement was considered to have been performed.

o For those welds whose data did not meet the BWRVIP-61 parame ters, an evaluation was to be performed to determine the effectiveness of the stress improvement.

As a result, the IHSI process for each weld was independently evaluated by Martin B. Sims in Southern Company Generation and Energy Marketing Power Engineering -

Metallurgy & Material Appli cations. Report Number 04-MT-086, "Plant Hatch Units 1 & 2 IHSI Effectiveness Review" is being i ssued by Metallurgy & Ma terial Applications to document the results. An E-Mail from M. B. Sims to M. Belford dated April 23, 2004 gave preliminary results which are shown below in italics. This E-Mail indicates that there is an issue with "proving" that the three dissimilar metal RHR welds had an effective IHSI process. Until other evidence is provided, these three RHR welds (2E11-

1RHRM-20RS-3, 2E11-1RHRM-24A-10, and 2E11-1RHRM-24B

-10) are considered as not having a effective IHSI process and are conservatively desi gnated as Category D.

Some minor deviations from the recommende d IHSI process parameters were noted, however, these deviations were either supported by mockup testing or not detrimental to IHSI effectiveness. As an example, the induction frequency was less than recommended 3-4 kHz range of BWRVIP-61 for all but one weld, but within the NUTECH procedure

limit of 3-4 kHz +/-10%. Based on discussi on with Tony Giannuzzi at Structural Integrity Associates (author of BWRVIP-61), a small reduction in induction frequency would produce deeper heating in the weld and not reduce IHSI effectiveness.

Therefore, these minor deviations in induction frequency do not affect IHSI effectiveness.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 2 Hatch 2 Basis Doc-VIP75.doc Page 40 of 40 Rev.1.0 Several nozzle-to-safe-end welds had outside surface temperatures outside the recommended range of 450-550 ºC in BWRVIP-6

1. These were within the limits of the originally recommended parameters of EPRI NP-2527-LD and NP-3375 (42575 ºC). A conservative upper limit was established in the original EPRI recommendations to prevent sensitization of the pipe surface, even though the IHSI heating time was not

long enough for this to occur and the outside surface of the pipe is not exposed to conditions conducive to IGSCC. Exceeding this limit has no effect on effectiveness of stress improvement and should be considered acceptable. The lower limit was established to ensure sufficient through-wall T with cooling water flows greater than the minimum recommended. Based on the IHSI Weld Package data, the minimum recommended 275 ºC through-wall T was determined to be met at surface temperatures of 438 ºC or greater. Ther efore, these nozzle-to-safe end welds are considered to have an effective stress improvement.

There are seven remaining welds in RHR that had recorded surface temperatures outside the recommended range of 450-550 ºC in BWRVIP-61. These were in Type 316NG material and were supported by a separate IHSI quali fication for 316NG materials. NUTECH evaluated the effe ctiveness of IHSI on type 316NG in a 1984 report prepared for Georgia Power Company (report XGP-08-111) and established IHSI parameters with expanded surface temperature ranges and a higher minimum T of 550 ºF (288 ºC) to achieve effective stress improvement in 316NG material. All other IHSI parameters were the same as previous EPRI recommendations. IHSI of type 316NG does not appear to be addressed by BWRVIP-61, however based on the NUTECH qualification of th e revised parameters and comp liance with the remaining recommended parameters of BWRVIP-61, thes e welds are considered to have an effective stress improvement.

An open issue remains on whether the induc tion coil length was effe ctively reduced by "shorting" the coils on the three dissimilar metal welds. There is no mention of this in the IHSI Weld Packages for the site implementation, however, Tony Giannuzzi recalled it was addressed in the IHSI calculation package s that SIA had reviewed for other sites.

I have not been able to locate any IHSI calc ulation packages for Hatch to review this concern. I will check with the SNC Design Modifications Group to determine if these calculations were filed with the DCR files. Additional effort could be required to try to locate the original calculations at former NUTECH offices or by hand searches of plant records. This would be time consuming and expensive, so you would need to determine if the effort is warranted to reduce inspect ion frequency for the four welds that are impacted. (Note: These welds are currently list ed as Category D welds, without credit being taken for IHSI).

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 2 Hatch Basis Doc Aug Other.doc Page 1 of 6 Rev. 1 The NRC's safety evaluation dated 6/16/97 of the 3 rd Interval ISI Program indicated, that in addition to the 1989 Code required examinations, certain augmented examinations would be performed per GPC commitment. The commitments along with the current implementation methodology are listed below and will also be followed for the 4 th Interval.

High Energy Lines Outside Containment Augmented examinations on the Unit 2 main steam, feedwater, HPCI (steam), RCIC (steam) and RWCU high energy piping outside containment (w here pipe breaks were not postulated) in compliance with Branch Technical Position MEB 3-1. Per Section 3.6.2.2.3 of the HNP-2 UFSAR, pipe breaks we re not postulated in portions of high-energy piping extending from the containment penetration to the first inside and/or outside isolation valve for sp ecified conditions. Therefore, for the above mentioned systems, volumetric exams are required on the welds between the inboard and outboard isolation valves to the extent practical. See Class 1 for a detailed evaluation.

Because these lines are also Class 1 lines for Section XI purposes, the high-energy Category B-J and XB-J welds are an integral part of the Class 1 Schedule Works tables.

Examination of IGSCC Susceptible Welds These examinations were originally performed per NUREG-0313 as modified by Generic Letter 88-01 and are currently performed per BWRVIP-075. A detailed evaluation is presented the BWRVIP-075 Section of this plan.

These welds are designated as Category OL-1, XB-J, and XB-F in the Schedule Works tables located in the BWRVIP

-075 Section of this plan.

Core Shroud Examination Examination of the core shroud in acco rdance with Generic Letter 94-03. These examinations were originally performed as required. They are currently performed per BWRVIP requirements.

Scram Discharge Volume Piping A detailed evaluation is presented the Class 2 Augmented portion of this plan. Schedule Works tables are listed in this section under Category C-0803.

These welds are designated as Category C-0803 in the Schedule Works tables located in this portion of the plan.

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 2 Hatch Basis Doc Aug Other.doc Page 2 of 6 Rev. 1 Feedwater Nozzles Augmented examination of the feedwate r nozzles as specified by NUREG-0619 as modified by Generic Letter 81-11. These examinations were originally performed as required. They are currently performe d per "Alternate BWR Feedwater Nozzle Inspection Requirements," GE-NE-523-A71-0594-A, Revision 1, May 2000.

From 1974 to 1980, the inspection of feedwate r nozzles by the industry indicated that there was some degree of cracking in the bore and inner radii of reactor vessel of reactor vessel feedwater nozzles in 18 of 23 commercially operating domestic BWRs. It was determined that most of the cracking wa s caused by lower temperature feedwater and CRD return line water leaking past interference fit spargers and initiating high-cycle thermal fatigue cracking in th e clad nozzle inner radius and bore region. Startup and shutdown cycles would then drive the crack deeper into the nozzle. As a result, on November 13, 1980 the NRC issued NUREG-0619 detailing specific requirements to alleviate the cracking. Additional guidance was given in Generic Letter 88-11. The NRC staff's position was that the nozzles should be de-clad, th e interference fit spargers replaced with an improved design, and the RW CU/CRD return lines re-routed such that the cooler water went through a ll the feedwater nozzles. The low-flow controllers should either be changed or a plant-specific fracture mechanics analysis should be performed that demonstrated that a crack would not grow to greater th an one inch during the 40 year life of the plant. The history for HNP-2 is shown below in the bulleted paragraphs The HNP RPV was originally fabricated with clad feedwater nozzles with interference fit spargers. The original nozzle confi guration is shown on CE drawing E 234-274 which can be found in the Hatch 1 Reactor Vessel Instruction Manual (S-19000). Because of cracking issues at other sites associated with the original configuration, the HNP-2 nozzle cladding was removed and a triple-sleeve, double piston sparger was installed per DCR 78-202. New feedwater nozzle configurations are shown in drawings SX-18920 and SX-18921.

"Edwin I. Hatch Nuclear Power Station, Unit 1, Feedwater Fracture Mechanics Analysis to Show Compliance with NUREG-0619" (NEDE-30238) was issued on August 1983 and submitted to the NRC by letter dated September 19, 1984.

By Safety Evaluation dated January 21, 1986 the NRC concluded that during the forty year life, the amount of fati gue crack growth in the feed water nozzles should be less than one inch, therefore, the existing Unit 1 flow controllers are in compliance with NUREG-0619 as amended by Generic Letter 88-11. Once compliance was determined, NUREG-0619 required (for the new triple-sleeve, double piston configuration) that a UT examination be performed on all feedwater nozzle bores and inside blend radii every 2 nd refueling outage and a PT of the ID be performed every 6 refueling outages or 135 startup/shutdown cycles.

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 2 Hatch Basis Doc Aug Other.doc Page 3 of 6 Rev. 1 By letter dated October 19, 1992, SNC proposed to perform an automated UT during the Spring 1993 outage and then UT every 4 th refueling outage in lieu of the NUREG-0619 requirements. The PT examination would thus be eliminated.

By NRC Safety Evaluation dated 10/21/94 and by SNC 10 CFR 50.59 Safety Evaluation dated 9/28/95 (HL-5040), the PT examination was eliminated and the frequency of the UT examinations was changed to every 4 th refueling outage.

Because of significant advances in UT inspection technology in the 1990's, the BWROG (using GE) began the development of alternate inspection requirements for the feedwater nozzles. As a result, BW ROG Licensing Topical Report, "Alternate BWR feedwater Nozzle Inspection Requirements", (GE-NE-523-A71-0594, Revision

0) was issued in October 1995 to allow reduced inspection frequencies.

A report were prepared by GE in July 1997 for HNP-2 as part of the Extended Power

Uprate effort, which (in part) provided feedwater nozzle fracture mechanics assessments based "upon the existing low flow feedwater controller in conjunction with plant operating history available at the time." The Extended Power Uprate increased the nominal operating pressure by about 50 psi and the feedwater nozzle temperature about 6 0 F. On February 9, 2000, GE issued a plant sp ecific evaluation for HNP to provide justification for extending the UT examina tion frequency of the nozzle inner radii and elimination of the ID PT examination. Th e evaluation was based on Revision 0 of the BWROG Topical Report and the NRC Safe ty Evaluation dated June 5, 1998. The evaluation noted that Revision 1 of the Topi cal Report, which incorporated responses to six NRC criteria, was submitted to the NRC on September 24, 1999. The evaluation further noted that the NRC's approval of the September 24 th submittal would have no effect on the evaluati on. Key issues and results are:

The evaluation per the BWROG Topical Report included consideration of the sparger type (triple-sleeve, double piston), UT inspection methodology (automated, full RF recording), and crack growth rate (b ased on the 1997 Extended Power Uprate feedwater nozzle fracture mechanics analysis).

The 1997 Extended Power Uprate feedwater nozzle fracture mechanics was used in determining the length of time that it would take to grow a 0.25" crack to unacceptable limits. Two criterion were used.

a. The first criterion was the time that it woul d take to grow the 0.25" crack to 1" in depth, which was the criteria found in NUREG-0619. It was concluded by the analysis that a crack would take greater th an 40 years to grow to a depth of 1" and that it would reach 0.87" in depth in 36 years.

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 2 Hatch Basis Doc Aug Other.doc Page 4 of 6 Rev. 1

b. The second criterion is more limiting and was based on the time it would take to grow a 0.25" crack to 10% of the blend radius thickness, which is the acceptable flaw depth per ASME Section XI. The blend radius was calculated by GE as 7.6" thick; therefore, the acceptable flaw depth would be 0.76". The time to grow a 0.25" crack to 0.76" deep was determined to be 32 years. GE indicated than a 10-year inspection frequency is appropria te based on the Extended Power Uprate fracture mechanics evaluation, a triple-sleeve, double-pi ston configuration, automated - full RF recording UT, and a blend radius thickness of 7.6".

On March 13, 2000 a letter was issued from D. M. Crowe (HNP Licensing Manager) to B. K. McLeod concluding that General Electric had performed the evaluation to change the inspection frequency to once per 10 years. The change was implemented per a 10 CFR 50.59 Evaluation dated 3/13/00.

In May 2000 GE issued, "Alternate BWR feedwater Nozzle Inspection Requirements", GE-NE-523-A71-0594-A, Revi sion 1, which incorporated the NRC's safety evaluation.

By letter dated September 23, 2003, the N RC approved the change to increase licensed power level for Hatch, Units 1 and 2 by 1.5 percent from 2763 megawatts thermal (MWt) to 2804 MWt. In the RPV St ructural Evaluation por tion of the safety evaluation it is stated that, "The proposed power uprate does not change the operating reactor pressure and temperature from th e current operating cond ition." Therefore, this change should not affect the fracture mechanics evaluation performed after the Extended Power Uprate.

Per Table 6-1 of GE-NE-523-A71-0594-A (NRC approved Alternate BWR Feedwater Nozzle Inspection Requirements) the Required Time between UT examinations of the Feedwater may be calculated as the Allowable Time multiplied by a Factor which is based on the sparger configuration and the type of UT examination. HNP-2 has a triple sleeve, double piston sparger configuration and uses automated - full RF recording UT. For an Allowable Time of 32 years the Required Time is 32 X 0.33 or 10.6 years ( 10 years). However, Note 2 of Table 6-1 indicates that a 10-year frequency is the maximum time between inspections for the blend radius area (region 1) and a portion of the nozzle bore (Region 2). Therefore, 10 years will be used as the frequency of examinations.

On December 3, 2003, discussions were held wi th Gary Stevens of Structural Integrity Associates. Per Gary Stevens's August 9, 1999 E-Mail (and reconfirmed during the 12/3/03 call) the use of 10% of wall thickness allowable flaw size for feedwater nozzles is based on Subsection IWB-3611 which permits an allowable flaw size of 10% of the critical size for normal operating conditions. In the case of the feedwater nozzle, the critical flaw size can be shown to be greater than the wall thickness, so the critical flaw size is set equal to the wall thickness, t. Thus, 0.10

• t is used for the allowable flaw size. It was confirmed that the blend radius was the most limiting area for crack growth; FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 2 Hatch Basis Doc Aug Other.doc Page 5 of 6 Rev. 1 therefore, GE's selection of 10% of the blend radius and a 10-year examination frequency was appropriate. Therefore, because the scheduling is the same as Code frequency these examinations will be treated as Category B-D, Item 3.100 Code examinations in ScheduleWorks. The only difference is that they are referred to as "Nozzle Inner Radius and Bore" examinations.

These welds are designated as Category B-D welds in the Class 1 portion of this document. CRD Return Line NUREG-0619 also addressed the examination of the Thermal Mixing Tee where CRD is routed to Feedwater. In this case, water from CRD mixes with RWCU at the mixing tee. There is a potential for cracking in the mixing zone. Therefore, the downstream thermal tee weld (2G31-2RWCU-4-2FW-33) is examined. This examination is not addressed in GE-NE-523-A71-0594-A; therefore, it will be continued each out age as required by NUREG-0619.

This weld is designated as Category C-0619 in Schedule Works in this portion of the plan. Class 2 Thin-Wall Piping The NRC's safety evaluation dated 6/16/97 of the 3 rd Interval Program also indicated, that in addition to the 1989 Code required examinations, volumetric examination of a 7.5% sample of a portion of thin-wall, non-ex empt piping within the RHR, CS, and HPCI systems would be performed. See Class 2 Augmented for a detailed evaluation.

These welds are designated as Category C-0803 in Schedule Works in this portion of the plan. RCIC Additionally, portions of the Reactor Core Isolation Cooling are designated as Class S on Boundary Diagram HB-16334 and HB-16335. It wi ll be treated usi ng Section XI as a guideline (not as a requirement). As discussed for the Class 2 portion of this piping, this system does not have an RHR, ECC, or CHR function; therefore, the size exemption and the pressure/temperature exemption will also be used for this Class S piping. Lines within Class S were evaluated below for examination potential.

6" Suction Line from the Condensate Stor age Tank (Designated as 1E51-2RCIC-6PS-1 thru 24 on Figure B-88 and listed as Category CF-R in Schedule Works). This piping is pressure/temperature exempt because it is at static pressure and ambient temperature; therefore, examination of piping welds, integrally welded attachments, and supports is not required.

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 2 Hatch Basis Doc Aug Other.doc Page 6 of 6 Rev. 1 6" Suction Line from valve 1E51-F031 through valve 1E51-F029 (Designated as 1E51-2RCIC-6TS-10, 11, 12, 13, and 14 on Figur e B-89 and listed as Category CF-R in Schedule Works). This piping is pressure/temperature exempt because it is highly unlikely that it would ever exceed the prescribed pressure/temperature. Therefore, examination of piping welds, integrally welded attachments, and supports is not required.

4" Pump Discharge Line - This piping is size exempt; therefore, examination of piping welds, integrally welded attachment s, and supports is not required. (Not shown in Schedule Works).

4" (and less) Steam Supply - This piping is size exempt; therefore, examination of piping welds, integrally welded attachment s, and supports is not required.. (Not shown in Schedule Works).

10" Steam Exhaust from the turbine to valve 1E51-F040 (Designated as 1E51-2RCIC-1 thru 24 and shown as Category CF-R in Schedule Works). This piping is shown on Figures B-24 and B-25 and is not pressure/temperature exempt because of the steam conditions. However, all of this piping is 0.365" nominal wall thickness and therefore does not require examinati on of the piping welds. The welded attachments and supports on this line are not subject to examination.

As discussed above, when applying Section XI requirements to Category S RCIC there are no requirements for examination. However, RCIC is an important system when considering PRA; therefore, a small sample of welds (designated as Category CF-R), Category supports (designated as Category FA-R), and welded attachments (designated as Category CC-R) were selected.