ML070430083

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

ML070430083
Person / Time
Site:	Hatch
Issue date:	02/06/2006
From:	Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML070430083 (557)

Text

SOUTHERN NUCLEAR OPERATING COMPANY MATERIALS AND INSPECTION SERVICES VOLUME 2 CLASS 1,2, AND 3 COMPONENTS FOURTH TEN-YEAR INSERVICE INSPECTION PLAN E. I. HATCH NUCLEAR PLANT UNIT 1 REVISION 1 REV 1 DESCRIPTION DATE 2/6/06 INITIAL ISSUE Site Site Stam --- PREP'D BY (M&IS) REV'D BY (M&IS) APPV. BY (M&IS) rj SITE REV'D BY APPR. PLANT P. MG.

SOUTHERN NUCLEAR OPERATING COMPANY MATERIALS AND INSPECTION SERVICES VOLUME 2 CLASS 1,2, AND 3 COMPONENTS FOURTH TEN-YEAR INSERVICE INSPECTION PLAN E. I. HATCH NUCLEAR PLANT UNIT 1 REVISION 1 11 HNP IS1 APPROVAL 11 I Written By: SNC-M&IS Department 11 11 QA Review: /z//& !I 1) AN11 Review: N A 11 1) PRB Review: N A 11 AGM-PS Appv:

/1//& (I AGM-PO Appv: / I HATCH UNIT 1 FOURTH INTERVAL EXAMINATION PLANS INTRODUCTION DISTRIBUTION H1 VOL1 DIST.doc Page 1 of 1 Rev. 1

Manual Manual Holder Number 1 Document Control QA Record Hatch Unit 1 Fourth Ten-Year Examination Plan List of Effective Pages H1 VOL2 EFFECTVE PAGES.DOC 1 of 2 Rev. 1 Volume 2 System Page Revision Distribution 1 1 Table of Contents 1-2 1 Introduction 1-27 1 Class 1 Exam Schedule Bases 1-37 1 Class 1 Code Compliance Sheets 8 pages Category B-A 1-5 1 Category B-D 1-6 1 Category B-F 1 1 Category B-G-1 1-25 1 Category B-G-2 1-6 1 Category B-J 1-35 1 Category NB-J 1-12 1 Category B-K 1-10 1 Category B-L-2 1 1 Category B-M-2 1-6 1 Category B-O 1 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 1-23 1 Category C-F-2 1-111 1

Class 3 Exam Schedule Bases 1-7 1 Class 3 Code Compliance Sheets 1 page 1 Category D-A 1-14 1

Supports Exam Schedule Bases 1-14 1 Supports Code Compliance Sheets 1 page 1 Category F-A, Item F1.10 1-8 1 Category F-A, Item F1.10S 1-6 1 Category F-A, Item F1.20 1-36 1 Category F-A, Item F1.20S 1-10 1 Category F-A, Item F1.30 1-25 1 Category F-A, Item F1.30S 1-4 1 Category F-A, Item F1.40 1-6 1 Category F-A, Item F1.40S 1-2 1

Hatch Unit 1 Fourth Ten-Year Examination Plan List of Effective Pages H1 VOL2 EFFECTVE PAGES.DOC 2 of 2 Rev. 1 Augmented Examinations VIP-075 Basis 1-46 1 Category OL-1 1-6 1 Category XB-F 1-2 1 Category XB-J 1-9 1

"Other" Augmented Examinations Bases 1-11 1 Category C-0619 1 1 Category C-0803 1-3 1 Category CF-R 1-6 1 Category FA-R 1-4 1 Category CC-R 1 1

Hatch Unit 1 Fourth Ten-Year Exam Plan TABLE OF CONTENTS H1 VOL2-T OF C.doc Page 1 of 2 Rev. 1 VOLUME 2 - Vessel and Piping Weld Information Distribution List of Effective Pages ASME Class 1 Exam Schedule Bases Class 1 Code Compliance Sheets Category B-A RPV Welds Category B-D RPV Nozzles (See Volume 4 for VIP requirements) 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 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)

ASME Class 3 Exam Schedule Bases Class 3 Code Compliance Sheets Category D-A Welded Attachments Component Support Exams - (Without Snubbers) 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 F1.40) Class 1, 2, and 3 Equipment Snubbers

Hatch Unit 1 Fourth Ten-Year Exam Plan TABLE OF CONTENTS H1 VOL2-T OF C.doc Page 2 of 2 Rev. 1

Augmented Examinations VIP-075 Basis 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 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 1 of 37 Rev. 1.0 SCOPE OF EXAMINATIONS Per IWA-1400 of the ASME 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 Class 1 components is made by Design Modifications and designated on the ISI Boundary Diagrams.

These Boundary Diagrams are controlled by Design

Modifications.

System Boundaries The system boundaries for Code Class 1 are designated on the ISI Boundary Diagrams.

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 Welded 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-H Integral Attachments for Vessels Category B-J Pressure Retaining Welds in Piping Category B-K Integral Attachment s for Piping, Pumps, and 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 Category B-N-2 Integrally Welded Core Support Structures/Interior Attachments Category B-N-3 Removable Core Support Structures Category B-O Pressure Retaining Welds in Control Rod Housings Category B-P Pressure Testing

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).

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 2 of 37 Rev. 1.0 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. This report used RCIC, CRD, and Condensate Makeup to the condenser as the makeup system and calculated. The same methodology will be used for the 4 th Interval; however, Condensate Make-up to the main condenser will be eliminated as a make-up source because the condensate pumps ar e 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 formulae for a leak rate at 1050 psi 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

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-11000), there are six Class 1 piping sp ecifications - DBA (Schedule 160), DCA (Schedule 80), DLA (Schedule 160), EAA (Schedule 80), EBA (Schedule 160), ands ELA (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" and smaller for Schedule 160 steam lines.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 3 of 37 Rev. 1.0 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-16061 Standby Liquid Control (SLC) System H-16062 Nuclear Boiler System Sheet 1 H-16063 Nuclear Boiler System Sheet 2 H-16064 CRD System Sheet 1 H-16065 CRD System Sheet 2 H-16066 Recirculation System Sheet 1 H-16067 Recirculation System Sheet 2 H-16068 Recirculation System Sheet 3 H-16145 Nuclear Boiler System Sheet 3 H-16188 Reactor Water Cleanup System Sheet 1 H-16189 Reactor Water Cleanup System Sheet 2 H-16329 RHR System Sheet 1 H-16330 RHR System Sheet 2 H-16331 Core Spray System H-16332 HPCI System Sheet 1 H-16333 HPCI System Sheet 2 H-16334 RCIC System Sheet 1 H-16335 RCIC 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-16066 and P&ID H-16188. (Reference isometric H-16817). These welds are shown on ISI Figures A-40 and A-41 and are designated as 1B31-1RC-2DR-1 through 50.

The 2" socket-welded drain line on each of the two loops as shown on P&ID H-16066. (Reference isometric S-01060). Th ese welds are shown on ISI Figure A-43 and are designated as 1B31-1RC-2A-1 through 8 and 1B31-1RC-2B-1 through 8.

The 1-1/2" socket-welded SLC line as shown on P&ID H-16061 and P&ID H-16063 (see isometrics H-16962 and H-16823). These welds are shown on ISI Figures A-44 and A-45. The socket welds are designate d as 1C41-1SBLC-1.5-1 through 33 and the butt welds on the safe-end are designated as 1C41-1SBLC-2-1 through 3.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 4 of 37 Rev. 1.0 The butt-welds on the N16A&B instrume nt nozzle safe-end. The welds on the N16A&B safe-ends penetrate the RPV in water space. Per S-15277A, each safe-end was fabricated using two pieces of bar stock (on Inconel and one stainless steel). The two pieces were welded together creating a dissimilar metal Category B-F weld. The combined safe-end was bored out to 1-15/16" diameter. The OD was prepped such that the OD diameter at the end away from the RPV was 2-13/32". The tolerance was plus 0" and minus 1/32 ". Applying th e tolerance, the OD is 2.375", which is the nominal diameter of a 2" pipe. It is assumed that there is a spool of 2" butt-welded pipe (containing three 2" Category B-J pi pe welds) connected to each safe-end and then a butt-welded socket weld coupling th at connects the 2" spool to the 1" EAA socket-welded piping. (See P&ID H-16063). For water, the IWB-1220(a) exemption is 1.09"; therefore, the butt welds are not exempt. Welds 1B11-1INST-2A-1 and 1B11-1INST-2B-1 are Category B-F weld s and welds 1B11-1INST-2A-2 through 5 and 1B11-1INST-2B-2 through 5 are Category B-J welds.

Based on the 5/4/93 memo from Bill Cole to Kevin White along with the associated

picture, access is available for the N16A Category B-F weld using access "from door above and to the right". N16B is not accessible. The memo states, "the depth of the bio-shield, air space, and insulation make the welds too deep for accessibility". A relief request will be needed for the Category B-F weld because all B-F welds must be examined per Code requirements.

Note: The N11A&B and N12A&B nozzles are the same size; however, they penetrate the RPV near the steam separator.

Inventory 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. These Code requirements may be deviated from by:

The use of NRC approved alternatives t 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.

Significant deviations from IWB-2500 Code requirements at HNP-1 include Code Cases, Relief Requests, Alternatives, and NRC Safety Evaluations as shown in Volume 1.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 5 of 37 Rev. 1.0 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. The original HNP-1 insu lation was ordered prior to the development of Regulatory Guide 1.36; however, GE was cognizant of the potential for OD stress corrosion cracking due to halogens in the insulation. Therefore, GE Specification 22A2807, Rev. 0 which provided the design requirements for HNP-1 insulation (see S-15393, Version 1.0) stated, "Insulating material for use on stainless st eel pipe is chosen because of its low chloride content and its corrosion inhibiting characteristics. It also required that leachable chlorides in the insulation be less than 300 ppm.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 6 of 37 Rev. 1.0 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: 54 of the large bore

piping welds are now covered with corrosion resistant overlay material). Additionally, ISI personnel associated with Hatch over the past 20 years have no knowledge of OD cracking in austenitic piping 4" diameter and over. (There has been OD originated cracking in some socket welds due to fatigue , but socket weld ar e not covered by Code Case N-663). Plant-specific processes and programs that minimize chlorides and other contaminants are:

The SNC purchase specification for thermal Insulation for SS require insulation suppliers to provide material that meet s 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 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 7 of 37 Rev. 1.0 ISI PLAN TABLES Beginning in 2005, ISI Plan Tables are generated by the industry standard ScheduleWorks ISI software. The following tables were generated 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 authorized IDDEAL software `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 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 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 8 of 37 Rev. 1.0 Category B-A - Class 1 RPV Item B1.11 and B1.12 Shell Welds Configuration The HNP-1 Reactor Pressure Vessel (RPV) has four Item B.11 circumferential welds - C-2, C-3, C-4, and C-5 and twelve Item B1.12 l ongitudinal welds - C-1-A, C-1-B, C-1-C, C-2-A, C-2-B, C-2-C, C-3-A, C-3-B, C-3-C, C-4-A, C-4-B, and C-4-C.

Background

1 st interval RPV shell weld examinations were performed to the requirements of the1974 Edition of Section XI (with Addenda through Summer 1975). Per the 1974 Edition only small portions of each longitudinal and circumferential weld were examined.

2 nd interval RPV shell weld examinations were originally scheduled to be performed per the 1980 Edition of Section XI and would have required completion prior to the end of the 2 nd interval. The 1980 Code required that one beltline circumferential weld and one beltline longitudinal weld be examined.

50.55a(g)(6)(ii)(A)(2) was added to 10 CFR 50.55a requiring that licensees augment their reactor pressure vessel 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 Ed ition of section XI (examination of all welds). However, per (A)(3) licensees with fewer than 40 months remaining in the inservice inspection interval in effect on September 8, 1992 could defer the augmented reactor vessel examination specified in (A)(2) to the first period of the next inspection interval. HNP-1, met this criteria; therefore, the augmented examinations were deferred until the 1st period of the 3rd interval.

Per 50.55a(g)(6)(ii) (A)(3) the deferred augmented examinations (which were scheduled for the 3 rd Interval) could not be used as a substitute for the 2 nd Interval reactor pressure vessel shell weld examinations scheduled for implementation during the inservice inspection interval in effect on September 8, 1992 (second interval). [Therefore, the 2 nd interval 1980 Code examinations were pe rformed in 1R16 (Spring 1996) using the 1 year Code extension provision of IWB-2412(b.

1 beltline region circ weld and 1 beltline region longitudinal weld were examined, thus completing the Second Interval shell weld examination requirements.

Per 50.55a(g)(6)(ii) (A)(3) the deferred augmented examination could be used as a substitute for the reactor vessel shell weld examination normally scheduled for the inspection interval in which the deferred examination is performed. [HNP-1 elected to use this option; therefore, 3 rd interval examinations were performed during the 1 st period of the 3 rd interval.

]

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 9 of 37 Rev. 1.0 Per 50.55a(g)(6)(ii) (A)(3), when the deferred augmented examination are used as a substitute for the normally scheduled reactor vessel shell weld examination, subsequent reactor vessel shell weld examinations must be performed during the first period of successive inspection intervals. [Therefore, HNP-1 4 th interval longitudinal weld examinations (including weld C-4-B if tec hnology exists) are scheduled during the 1 st period of the 4 th interval. (1R23).

] In September 1995, BWRVIP-05 was issued to the NRC defining a technical basis for eliminating the examination of the Item B 1.11 circumferential welds. HNP elected to request approval to use BWRVIP-05 as a basis for the elimination of the circumferential weld examinations for the 3rd interval examinations.

Because of the complexity of the augmented regulations and the request for elimination of the circumferential weld examinations, a timeline is presented below for the 2 nd and 3 rd interval examinations shell weld examinations.

By letter dated December 4, 1995, GPC requested that previous relief requests be re-instated for the shell welds such that above provisions could be ut ilized. This letter also clarified the position th at the Second Interval shell weld examinations would be performed in the first period of the Third Interval. By letter dated February 14, 1996 the NRC agreed. Examinations were de ferred until Spring 1999 refueling outage.

Spring 1996 - Because the augmented examinations could not be used as a substitute for the reactor vessel shell weld examination scheduled for implementation during the inservice inspection interval in effect on September 8, 1992, 2 nd interval 1980 Code examinations (1 beltline region circ weld and 1 beltline region longitudinal weld) were performed in 1R16 (Spring 1996) usi ng the 1 year Code extension provision of IWB-2412(b). Second Interval shell weld examination requirements were thus completed.

September 1997 - Augmented 1989 Section XI HNP-1 longitudinal weld examinations were performed from the OD during the 1 st period of the 3 rd interval (1R17). These examinations were credited as 3 rd interval examinations as allowed by 50.55a(g)(6)(ii) (A)(3

). OD examinations were performe d on the accessible portions of C-1-A, C-1-B, C-1-C, C-2-A, C-2-B, and C-2-C longitudinal shell welds. Circumferential welds were not examined anticipating approval of BWRVIP-05.

By letter dated July 28, 1998 the NRC issu ed their generic safety evaluation for BWRVIP-05 with conditions. Note: A supplement to the safety evaluation was added by NRC letter dated March 7, 2000.

By letter dated October 16, 1998, SNC reque sted approval to delete the HNP-1 circumferential shell welds for the Spring 1999 outage (1R18) using BWRVIP-05 as the basis.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 10 of 37 Rev. 1.0 On November 10, 1998, the NRC issued Generic Letter 98-05 to inform licensees that they could request permanent (term of the original license) relief for the volumetric examination of circumferential shell welds.

By letter dated December 2, 1998, SNC submitted an alternative to the augmented requirements to allow HNP-1 to:

1. Permanently defer the volumetric examination of the circumferential welds based on the BWRVIP-05 requirements.

2. Allow reduced coverage of certain welds.

3. Use the GERIS-2000 system as the ultrasonic examination technology.

By letter dated December 15, 1998, the VIP responded to the questions in the NRC's July 28, 1998 SE.

By letter dated January 19, 1999, SNC altered the above request by amending coverage requirements showing both OD and ID anticipated coverage.

By letter dated February 5, 1999, SNC responde d to staff questions regarding shell weld coverage and also committed to notifying the NRC if coverage was not within +

4% of that shown in the January 19, 1999 letter.

Spring 1999 - Augmented 1989 Section XI longitudinal examinations were performed from the ID during the 1 st period of the 3 rd (1R18). Examinations were performed on longitudinal shell welds C B and C-2-C to obtain additional coverage beyond that obtained during the OD examinations. Examinations were performed, as the only coverage, on longitudinal shell welds C-3-A, C-3-B, C-3-C, C-4-A, C-4-B.

There was no coverage on C-4-C due to a tie rod obstruction.. Circumferential welds were not examined anticipating approval of SNC's alternativ e to use BWRVIP-05.

By letter dated March 11, 1999, the NRC issu ed their SE giving HNP-1 approval to permanently defer the examination of circumferential shell welds C-2, C-3, C-4, and C-5 and for the coverage of the longitudi nal shell welds. (This was granted per 10CFR50.55a(3)(i); however, it was unclear as to what the NRC was granting).

However, the NRC still requires a volumetric examination of C-4-B if SNC ever removes an obstructing tie rod or technology becomes available to perform the examination with the tie rod in place.

By SNC letter dated April 26, 1999, the NRC was notified that the coverage on longitudinal shell weld C-3-A was 7.6% le ss than identified in the January 19, 1999 letter. By NRC letter dated March 7, 2000, the NRC i ssued the SE for VIP-05 with regard to the VIP letter dated July 28, 1998.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 11 of 37 Rev. 1.0 Due to the confusion in the March 11, 1999 safety evaluation, by SNC letter dated March 29, 2004 (as supplemented by letter dated September 13, 2004) SNC requested permanent approval for not examining the B1.11 circumferential shell welds via RR-

38. Because the RAMA Code used for the neutron fluence had not been approved by the NRC, the NRC limited the duration of RR-38 until July 31, 2007.

Fourth Interval Examinations(Items B1.11 and B1.12) 4th Interval of the longitudinal shell welds (Item B1.12) are scheduled for 1R23 (February 2008) during the 1 st period of the 4 th interval as required.

RR-38 is in effect only until July 31, 2007 (to eliminate the circumferential shell weld examinations) and a new alternative will be required.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 12 of 37 Rev. 1.0 Category B-A - Class 1 RPV Item B1.21 and B1.22 Head Welds Configuration The HNP-1 bottom head has 14 meridional welds BHD-A thru F, BHT-A thru H, circumferential dollar plate weld C-8, and ci rcumferential weld C-7. The design is such that there is a support skirt welded to the bottom head just in side of weld C-7. There is no access to welds located inside the support skirt. Therefore, meridional welds BHD-A thru F are basically inaccessible except for a few inches of each weld that extends out past the skirt. Circumferential weld C-8 is completely inaccessible.

Background

During the 1 st Interval, Examinations were performed to the requirements of the1974 Edition of Section XI (with Addenda through Summer 1975). Per the 1974 Edition, 5% of each accessible circumferential weld and 10% of each accessible meridional weld were examined.

During the 2 nd Interval, examinations were performed per the 1980 edition of Section XI, which required that one circumferential weld and one meridional weld be examined. Deferral of the examinations until the end of the 10-year interval was permissible, but not required. Second interval examinations were performed as follows.

Bottom Head Circumferential Welds - We ld C-7 is the only accessible B1.21 circumferential weld. This weld was examined during the 3 rd period (1993).

Bottom Head Meridional Welds - Weld BHT-E was examined during the 3 rd period (1993). Closure Head Circumferential Welds - Weld HC-1 is the only B1.21 circumferential weld. This weld was examined during the 2 nd period (1990).

Closure Head Meridional Welds - Weld HC-1-D was examined during the 1 st period (1987).

During the 3 rd Interval, examinations were performed as follows:

Bottom Head Welds Examinations were required per the 1989 edition of Section XI which required examination of all circumferential and meridional welds. However, because of the support skirt configuration, meridional welds BHD-A thru F are basically inaccessible and weld C-8 is completely inaccessible. These welds were examined during the third period (1R22) using Appendix VIII techniques.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 13 of 37 Rev. 1.0 Per the Unit 1 RPV Examination Plan prepared by GE, all of the HNP-1 meridional and circumferential welds were fabricated using the Upjohn process. In the Upjohn process, the weld beads are applied in the flat position with longitudinal progression along the weld seam such that weld beads are perpendicular to seam as opposed to weld beads running with the seam. Therefore, any slag-like construction flaws would be oriented longitudinally and only the minor axis of Upjohn weld flaws would have been seen

during construction radiography. Thus, slag-like construction flaws may have been characterized as small inclusions.

GE SIL 651 was issued on August 7, 2003, to not ify 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 ISI examinations at Fermi did not report theses flaws; however, re-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.

Closure Head Welds Closure head welds are Upjohn welds but were examined in the 3 rd interval prior to the implementation of Appendix VIII. Examinations completed during the 3 rd interval were::

Closure Head Circumferential Welds - Weld HC-1 is the only B1.21 circumferential weld. This weld was examined during the 2 nd period (1R19); therefore, all 3 rd interval examinations were complete.

Closure Head Meridional Welds - Welds HC-1-A, HC-1-B, HC-1-C, and HC-1-D were examined during the 1 st period (1R18). Welds HC-1-E, HC-1-F, HC-1-G, and HC-1-H were examined during the 2 nd period (1R19). Therefore, all 3 rd interval examinations were complete.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 14 of 37 Rev. 1.0 Fourth Interval Examinations Bottom Head Circumferential Welds (Item B1.21) - C-7 and C-8 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 permitted. Weld C-7 is scheduled for examin ation during the 3 rd Period of the 3 rd Interval (1R22) to complete the 3 rd Interval requirements; therefore 4 th Interval examinations will be performed during the 3 rd Period of the 4 th Interval (1R27). [Weld C-8 is completely inaccessible and will require NRC approval.]

Closure Head Circumferential Welds (Item B1.21) - HC-1 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 permitted. Weld HC-1 is the only B1.21 circumferential weld on the closure head. This weld was examined during the 2 nd period (1R19) of the 3 rd Interval; therefore, the 4th interval examination is scheduled for 1R24.

Bottom Head Meridional Welds (Item B1.22) - BHD-A thru F and BHT-A thru H 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 permitted. These welds are scheduled for examination during the 3 rd Period of the 3 rd Interval (1R22) to complete the 3 rd Interval requirements; therefore 4 th Interval examinations will be performed during the 3 rd Period of the 4 th Interval (1R27). Note: Because of the support skirt configuration, meridional welds BHD-A thru F are basically inaccessible.

Closure Head Meridional Welds (I tem B1.22) - HC-1-A through H 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 permitted. Welds HC-1-A, HC-1-B, HC-1-C, and HC-1-D were examined during the 1 st period (1R18) of the 3 rd Interval and are scheduled to be examined in the 1 st Period of the 4 th Interval (1R23). Welds HC-1-E, HC-1-F, HC-1-G, and HC-1-H were examined during the 2 nd Period (1R19) of the 3 rd Interval and are scheduled to be examined in the 2 nd Period of the 4 th Interval (1R24).

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 15 of 37 Rev. 1.0 Category B-A - Class 1 RPV Item B1.30 and B1.40 RPV Flange Welds Configuration There is one RPV-to-flange weld and one closure head-to-flange weld.

Background

During the 1 st interval, approximately 1/3 rd of the RPV-to-flange circumference was examined each period and approximately 1/3 rd of the closure head-to-flange circumference was examined each period.

During the 2 nd interval, approximately 1/3 rd of the RPV-to-flange circumference was examined each period and approximately 1/3 rd of the closure head-to-flange circumference was examined each period.

During the 3 rd Interval the following logic was used for examination of these welds.

These welds were not deferrable by Code because:

1. Partial examinations were not being performed from the flange face as allowed by footnote 3.

2. The deferral provision does not apply to units that examine RPV nozzles from the OD.

However, these two welds were the only non-de ferrable welds in Category B-A, and per Relief Request RR-28 two components could be scheduled at any time during the interval; therefore, the welds were not included in IWB-2412(a) Code percentage calculations. 100% of the weld was examined during the 1 st Period of the 3 rd Interval (1R17) to re-zero the exams.

Fourth Interval Examinations RPV Shell-to-Flange Weld (Item B1.30) - C-1 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 permitted per Note 5 of Category B-A, Table IWB-2500-1. One third of the examinations were performed each

period in the second interval. 100% was subsequently performed during the 1 st Period of the 3 rd Interval (1R17) to re-zero the exams.

100% was then scheduled during the 1st period of the 4 th Interval (1R22a).

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 16 of 37 Rev. 1.0 RPV Head-to-Flange Weld (Item B1.30) - HC-2 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 permitted per Note 5 of Category B-A, Table IWB-2500-1. One third of the examinations were performed each

period in the second interval. 100% was subsequently performed during the 1 st Period of the 3 rd Interval (1R17) to re-zero the exams.

100% was then scheduled during the 1st period of the 4 th Interval (1R22a).

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 17 of 37 Rev. 1.0 Category B-D - Class 1 Full-Penetration Nozzle to Vessel Welds Configuration There are 29 RPV nozzles with full-penetration welds with each nozzle requiring Section XI ultrasonic examinations of the weld and the inner radii for a total of 58 examinations.

The N15 RPV drain nozzle is located inside the support skirt and is not accessible. The SE for RR-3 grants 3 rd interval approval to not perform the required examinations for N15. Therefore, there are 56 examinations that must be scheduled and conducted per Code requirements.

Feedwater nozzle examinations have historically been covered by the requirements of Section XI and the augmented examination requirements of NUREG-0619 as amended by Generic Letter 88-11.Section XI requires examination of the nozzle-to-shell weld and inner radius once per 10-year interval. Because of cracking in the inner radius areas of other BWRs due to leakage around interference fit thermal sleeves, the HNP-1 interference fit thermal sleeves were replaced with triple-sleeve, double piston design. Per NUREG-0619 augmented examinations of the feedwater nozzle inner radius (and bore) for a triple-sleeve, double piston 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 confi gurations, the frequency is now once per interval (see "Feedwater Nozzle Augmented Requirements" later in this document for detailed discussion). Background All Feedwater nozzles and inner radii were re-examined in the 1 st period of the 3 rd interval to enhance the scheduling of automa ted nozzle examinations. Per Footnote 2 of Table IWB-2500-1, Category B-D, at least 25% but not more than 50% (credited) of the 56 nozzle examinations were examined by the end of the first inspection period, and the remainder by the end of the inspection interval.

There are 56 examinations that must be scheduled and conducted per Footnote 2. During the 1 st Period a total of 22 examinations were performed or 39%. The remainder of the examinations were completed during the 2 nd and 3 rd periods.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 18 of 37 Rev. 1.0 Fourth 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 N15 nozzle due to inaccessibility.

Note: Per NUREG-0619 augmented examinati ons of the feedwater nozzle inner radius (and bore) for a triple-sleeve, double pi ston 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 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 19 of 37 Rev. 1.0 Category B-E - Class 1 Partial Penetration RPV Welds

Category B-E includes 137 CRD partial penetr ation stub tube welds to the RPV and 7 partial penetration instrument nozzle welds to the RPV. These are:

1N10 SLC Nozzle (Sketch 1-BE-2) 1N11A, B Instrument Nozzles (Sketch 1-BE-1) 1N12A, B Instrument Nozzles (Sketch 1-BE-1) 1N16A,B Instrument Nozzles (Sketch 1-BE-1)

137 - CRD Penetrations - Partia l penetration weld is on the inside of the RPV. (Sketch 1BE-3): Note: Listed as one set of examinations in Schedule Works.

Background

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 requirements.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 20 of 37 Rev. 1.0 Category B-F - Class 1 Dissimilar Metal Piping Welds (Less Than 4" NPS (B5.20)

Nozzle Requirement Evaluation 1B11\N10 Standby Liquid Control Surface examination of Inconel Nozzle-To-304SS Safe End Inconel 182 weld and butter designated as:

1C41-1SBLC-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 1BE-2 this line (1C41-1SBLC-2-1) has an inside diameter of 1.915" 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. See ISI Figure A-44. [Accessible per a 5/4/93 memo from K. White to B. Cole]. 1B11\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 1BE-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]. 1B11\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 1BE-1 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]. 1B11\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. 1B11\N16A&B Instrument Nozzles

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

1C41-1SBLC-2A-1 1C41-1SBLC-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 ISI Figure A-42, 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. Welds located on the N16A safe-end are accessible; however, welds on the N16B safe-end are not accessible per 5/4/93 memo from Kevin White to Bill Cole. A Relief Request will be needed for the 4 th Interval for weld 1C41-1SBLC-2B-1as shown on Figure A-42.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 21 of 37 Rev. 1.0 Category B-F - Class 1 Dissimilar Metal Piping Welds (Continued)

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 Valve to Pup-Piece Welds 1 - CRD Return Line Nozzle to Cap

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 has been requested from the NRC per ISI-ALT-3 to continue to eliminate the B-F welds from Code required percentages and fr equency that originated with RR-39 in the 3 rd Interval.ISI-ALT-3 was approved by the NRC by safety evaluation dated 12/22/05.

SEE CATEGORY X-BF FO R VIP-075 REQUIREMENTS

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 22 of 37 Rev. 1.0 Category B-G Class 1 Pressure Retainin g Bolting Greater Than 2" in Diameter

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

RPV Bolting 52 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-es tablished pattern, 33% is scheduled for the 1 st Period, a cumulative total of 66% is sc heduled by the end of the 2 nd Period, and 100% by the end of the 3 rd Interval.

RPV Studs (Item B6.30) - Per Code Case N-307-3, the surface examinations required when studs are removed was eliminated. Without the surface examination requirement, there is no difference between Item B6.20 and item B6.30; therefore, all studs are treated as Item B6.20.

52 RPV Studs (Item B6.20) - During the 4 th Interval, examinations will be performed per Code Case N-307-3 and the 2001 Edition of the Section XI Code through the 2003 addenda. The Code allows deferral of the examinations until the end of the interval and Code Case N-307-3 defines the examination volume. During the 3 rd Interval, per the provisions in Relief Request RR-35 (granted by Safety Evaluation dated July 2, 2002), all 52 studs were examined during 3 rd Period (1R21). Therefore, during the 4 th Interval, examinations are scheduled during the 3 rd Period.

52 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 the examinations until the end of the interval. During the 3 rd Interval, per the provisions in Relief Request RR-35 (granted by Safety Evaluation dated July 2, 2002), all 52 were examined during 3 rd Period (1R21). Therefore, during the 4 th Interval, examinations are scheduled during the 3 rd Period.

52 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, during the 3 rd Interval scheduling was performe d per Code Case N-598. Continuing the pre-established pattern, 17 are scheduled for the 1 st Period, 17 are scheduled during the 2 nd Period, and 18 are scheduled during the 3 rd Interval.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 23 of 37 Rev. 1.0 RPV Bushings (Item B6.50B) - During the 4 th Interval, examinations will be performed per the 2001 Edition of the Section XI Code through the 2003 addenda. The Code allows deferral of the examinations until the end of the interval. The bushings are threaded inserts that are thread ed into the threaded flange hole. The RPV studs are then threaded into the bushings. Studs 32, 33, 35, and 35 are normally removed during refueling outages and the bushings should be VT-1 examined one time during the 10-year interval. Per In tent Inquiry IN04-009 (BC04-1733), bushings are not required to be examined unless the studs are removed.

Note: If other studs are removed examine the associated bushings.

Examinations are scheduled as shown in the attached Hatch Unit No. 1 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 1R20 (2 nd period), 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 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. Examinations 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 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 24 of 37 Rev. 1.0 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.

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:

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 25 of 37 Rev. 1.0 Valve Bolting Valve Group Number 1B21-F010A&B and F032A&B VB 1 1B21-F011A&B VB 2 1B21-F013A, B, C, D, E, F, G, H, J, K, L VB 3 1B21-F022A thru D and F028A thru D VB 4 1B31-F023A&B and F031A&B VB 5 1E11-F008 and F009 VB 6 1E11-F015A&B VB 7 1E11-F067 VB 8 1E11-F050A&B VB 9 1E11-F060A&B VB 10 1E21-F004A&B and F005A&B VB 11 1E21-F006A&B VB 12 1E21-F007A&B VB 13 1E41-F006 VB 14 1E41-F002 and F003 VB 15 1G31-F001 and F004 VB 16 1G31-F027 VB 17

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 26 of 37 Rev. 1.0 Category B-J - Class 1 Piping Welds

Background

During the 1 st Interval welds were selected and examined per Category B-J of Section XI of the ASME Code in the 1974 Edition and addenda through the Summer 1975. This Code requires a selection of 25% of the B-J welds with the in tent that a different 25% be examined each 10-year interval. During the 2 nd Interval, the 1980 Code required a stress based selection of welds. In response, the NRC developed 10CFR 50.55a(b)(2)(ii), which states, "If the facility's application for a construction permit was docketed prior to July 1, 1978 (HNP-1 was docketed prior to this date), 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 Hatc h Unit No. 1 was docketed prior to July 1, 1978.

The 2 nd Interval ISI Program submitted to the NRC stated, "The extent of examination of Code Class 1 (Category B-J) was determin ed by the requirements of Table IWB- 2600 Category B-J of Section XI of the ASME Code in the 1974 Edition with addenda through the Summer 1975 Addenda as allowed by 10 CFR 50.55a. In addition, terminal ends and high stress welds were chosen when practical to upgrade the overall selection criteria".

The 3 rd Interval ISI Program submitted to the NRC stated, "As allowed by 10CFR50.55a(b)(2)(ii), Category B-J welds to be examined in Interval 2 were also selected to 1974/S75. In keeping with the later Code philosophy of re-examining components in subsequent intervals, essentially the same 25% scope was picked for Interval 2 as was picked for Interval 1.

The scope was adjusted, as a conservative measure, by selecting terminal ends and high stress welds to the extent practical. As allowed by 10CFR50.55a(b)(2)(ii), the scope of B-J welds for Interval 3 will be essentially the same 25% scope as for Interval 2 (accordingly, the footnotes of Table IWB-2500-1 will not be used). Variations may be made to account for ALARA goals and limited access as long as the required number of welds are examined."

Relief was received from the NRC (See RR-38) during the 3 rd Interval to not meet the following 1989 Code requirements for stainless steel welds and dissimilar metal welds. In lieu of these Code requirements the schedules and frequencies specified in the

BWRVIP-75 were used for stainless steel and dissimilar metal welds. Therefore, the only Category B-J welds that were scheduled per Section XI (at the end of the interval) were the carbon steel welds.

o 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 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 27 of 37 Rev. 1.0 Table IWB-2412-1. Table IWB-2412-1 defines a minimum and maximum number of examinations to be performed each inspection period.

o 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.

4 th Interval ISI-ALT-3 was submitted to the NRC to continue the process initiated by RR-39;

therefore, those welds cove red by the provision s of BWRVIP-075 ar e 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. Five of these eight welds were examined during the 3 rd Interval. No change will be made for the 4 th Interval.

There are 12 containment penetration with a weld to the flued head located inside the penetration and one located outside the penetration. This is an anchor point for stress analysis, but is not the extremity of the piping run; therefore, it is not considered a terminal end. Four were examined in the 3 rd Interval. No change will be made for the 4 th Interval.

There are approximately 19 cases where a smaller line terminates at a branch connection or terminates at a tee on a larg er line. For the connection of a piping 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 diameters is 10 to 1 or greater, the connection is consid ered to be a terminal end. None of the 19 cases had a 10/1 or greater ratio; therefore, there are no terminal HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 28 of 37 Rev. 1.0 ends in this population. A total of 5 of the 19 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 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 52 13 25% 18" FW 25 7 28% 4" MS 1 0 0% 24" MS 93 24 26% 8" MS 22 6 27% 20" RHR 12 3 25% 24" RHR 22 6 23% 9" RHR 2 1 50% 10" CS 40 9 23% 10" HPCI 21 5 24% 14" HPCI 12 3 25% 3" HPCI 3 1 33% 3" RCIC 2 0 0% 4" RCIC 32 8 25% 6" RCIC 2 1 50% 4" RWCU 3 1 33% 3" RWCU 1 0 0% TOTAL 345 88 25%

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 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 29 of 37 Rev. 1.0 (Shown as Category NB-J in Schedule Works) Size Fig. Item System No. of Welds Welds Examined Percentage 2" A-42 NB9.21 1B11 8 2 25% 2" A-40 A-41 NB9.40 1B31 50 12 24% 2" A-43 NB9.40 1B31 16 4 29% 2" A-43 NB9.32 1B31 2 0 0% 2" A-44 NB9.21 1C41 2 1 50% 1.5" A-44 NB9.40 1C41 3 1 33% 1.5" A-45 NB9.40 1C41 30 9 29% TOTAL 111 29 26%

These examinations are not deferrable until the end of the interv al per the 1989 Code; therefore, the scheduling requirements of Code Case N-598 are required.

SEE CATEGORY X-BJ FO R VIP-075 REQUIREMENTS

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 30 of 37 Rev. 1.0 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 brackets.

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-1 RPV is supported by a reactor skirt (weld C-6) and has four stabilizer brack ets (SB1 - SB4) 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-1, the configuration does not match Figure 14; therefore, HNP will use Code Case HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 31 of 37 Rev. 1.0 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-1 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 ALTERNATIVE (SEE 3 rd INTERVAL RR-41)

Item B10.20 - Piping: Per the Code, 10% of the piping welded attachments must be examined. There are 79 sets of Class 1 attachments requiring a tota l of eight sets of examinations be performed.

Note: There are three types of containment penetrations for HNP-1. (See Section 5.2 of the FSAR for description of penetrations). Only one type, where thermal movements are small, has an attachment weld to the pre ssure boundary of the pipe. This type of penetration has not been found in the Class 1 sc ope. The other penetrations involve flued heads and expansion bellows. In these cases, the attachment welds are located outside the "1t" boundary, where "t" is the thickness of the pressure-retaining pipe (See Figures IWB-2500-13, 14, and 15 for "t"). Therefore, there are no attachment welds at the containment penetrations in the B10.20 scope.

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 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 32 of 37 Rev. 1.0 Category B-L Pressure Retaining Welds in Pump Casings NA

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 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 33 of 37 Rev. 1.0 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.

For Hatch the groupings are:

Valves Group No. 1B21-F010A&B and F032A&B 1 1B21-F011A&B 2 1B21-F013A, B, C, D, E, F, G, H, J, K, L 3 1B21-F022A thru D and F028A thru D 4 1B31-F023A&B and F031A&B 5 1E11-F008 and F009 6 1E11-F015A&B 7 1E11-F067 8 1E11-F050A&B 9 1E11-F060A&B 10 1E21-F004A&B and F005A&B 11 1E21-F006A&B 12 1E21-F007A&B 13 1E41-F006 14 1E41-F002 and F003 15 1G31-F001 and F004 16 1G31-F027 17 If one of the valves is disassembled for maintenance or repair, a VT-3 examination of the accessible internal pressure boundary should be performed to th e extent pr actical. Examinations are limited 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 during the 10-year interval. There is not a requirement to disassemble a valve in order to perform the VT-3 examination.

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). 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 a more extensive examination is allowed, perform a VT-3 examination on the recently disassembled valve.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 34 of 37 Rev. 1.0 Examinations were performed as shown in the attached Hatch Unit No. 1 Code Compliance Scheduling Summary - 3 rd Interval for Items B12.50.

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 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 35 of 37 Rev. 1.0 Category B-N RPV Interior See Vessel Internals Notebooks Category B-N RPV Core Support Structure and Attachments See Vessel Internals Notebooks HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 36 of 37 Rev. 1.0 Category B-O - Pressure Retaining Welds in Control Rod Drive (CRD) Housings Configuration

The bottom head of the RPV has a penetration for each CRD location. Each penetration had an Inconel SB-167 stub tube welded to the inside surface of the RPV bottom head with an Inconel 182 weld. The CRD housing was raised into position inside the stub tube and fastened with a J-Groove weld to the st ub tube. The J-Groove weld had an Inconel 82 root with the remainder of the weld Inconel 182. (See Figure 2-BE-4 and FSAR Figure 4.2-12). Outside of the RPV, there is a housing to flange weld (and there may be an intermediate housing to housing weld between the flange weld and the bottom of the vessel.) Note: These welds are inaccessibl e due to being inside the support skirt.

The 2002 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.

ALTERNATIVE NEEDED BECAUSE OF THE INACCESSIBILITY.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 1 COMPONENTS Hatch 1 Basis Doc-Class 1.doc Page 37 of 37 Rev. 1.0 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 1 main steam, feedwater, HPCI (steam), RCIC (steam) and RWCU high energy piping outside containment (where pipe breaks were not postulated) are not require

d. This is based on the information supplied in a December 1972 NRC letter from A. Giambusso to Georgia Power Company. 2. Augmented examination of welds susceptible to IGSCC as specified in NUREG-0313 as modified by Generic Letter 88-01. These examinations were originally performed as required. They are currently performed per BWRVIP-075. See the BWRVIP-75 Section of this document.

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

4. Examination of the core shroud in acco rdance with Generic Letter 94-03. These exams are currently performed per BWRVIP requirements (non-ASME).

Southern Nuclear Operating Company Page I - 113012006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-A 81.11 4 0% 0 0 0 B-A B1.12 12 100% 12 12 12 Total: 16 12 12 12 ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 12 100.00% 100% 12 100% 100% ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 0 100.00%

100% 0 100% 100% ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 0 100.00% 100% 0 100% 100%

Southern Nuclear Operating Company Page 1 - 113012006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 ACTUAL ROUND 1 COYNT PERIOD UP 1 100.00% 100% PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-A B1.21 3 66.67% 2 2 2 B-A 81.22 22 100% 22 22 22 Total. 25 24 24 24 ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 4 18.18% 19% 4 16.60% 17% ACTUAL ROUND COUNT PERIOD UP 1 50.00% 50% 4 36.36% 37% 5 37.50% 38%

Southern Nuclear Operating Company Page 1 - 113012006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS 8-A 81.30 1 100% 1 1 1 8-A 81.40 1 100% 1 1 1 Total: 2 2 2 2 ACTUAL ROUND COUNT PERIOD UP 1 100.00% 100% 1 100.00% 100% 2 100% 100% ACTUAL ROUND COUNT PERIOD UP 0 100.00% 100% 0 100.00% 100% 0 100% 100% ACTUAL ROUND COUNT PERIOD UP 0 100.00% 100% 0 100.00% 100% 0 100% 100%

Southern Nuclear Operating Company Page 1 - 2/1/2006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-G-1 B6.10 52 100% 52 52 52 B-G-1 86.20 52 100% 52 52 52 B-G-1 86.40 52 100% 52 52 52 B-G-1 86.50 52 100% 52 52 52 B-G-1 B6.50B 4 0% 0 0 4 Total: 212 208 208 212 ACTUAL ROUND COUNT PERIOD UP 17 32.69% 33% 0 0% 0% 0 0% 0% 17 32.69% 33% 0 0% 0% 34 16.30% 17% ACTUAL ROUND COUNT PERIOD UP 17 65.38% 66% 0 0.00% 0% 0 0.00% 0% 17 65.38%

66% 0 0% 0% 34 32.60%

33% ACTUAL ROUND COUNT PERIOD UP 18 100.00%

100% 52 100.00%

100% 52 100.00% 100% 18 100.00%

100% 4 0% 0% 144 101.00% 101%

Southern Nuclear Operating Company Page 1 - 113012006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-G-1 B6.180 32 50% 16 16 16 B-G-1 B6.190 2 100% 2 2 2 B-G-1 86.200 2 50% 1 1 2 Total: 36 19 19 20 ACTUAL ROUND COUNT PERIOD UP 16 100.00%

100% 0 100.00% 100% 0 200.00% 200% 16 105.00% 105% ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 2 100.00% 100% 2 200.00% 200% 4 21.00% 21% ACTUAL ROUND COUNT PERIOD UP 0 100.00% 100% 0 100.00% 100% 0 20O.0O0h 200% 0 105.00% 105%

Southern Nuclear Operating Company Page 1 - 1/30/2006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-J B9.11 324 25% 8 1 8 1 82 B-J B9.21 5 25% 1.25 2 1 B-J B9.31 13 25% 3.25 4 4 B-J B9.32 3 25% 0.75 1 1 Total: 345 86 88 88 ACTUAL ROUND COUNT PERIOD UP 3 1 38.27% 39% 0 0% 0% 2 61.54% 50% 0 0% 0% 33 38.30% 38% ACTUAL ROUND COUNT PERIOD UP 17 59.26%

60% 1 80.00% 50% 0 61.54% 50% 0 0.00% 0% 18 59.30% 58% ACTUAL ROUND COUNT PERIOD UP 34 101.23% 102% 0 80.00% 50% 2 123.08% 100% 1 133.33% 100% 37 102.00% 100%

Southern Nuclear Operating Company Page 1 - 1/30/2006 Code Compliance Scheduling Summary - 4th Interval IS[.- Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 ACTUAL ROUND COUNT PERIOD UP 0 20.00% 20% 3 101.27%

100% 0 166.67%

100% 3 71.40% 72% ACTUAL ROUND COUNT PERIOD UP 0 20.00% 20% 3 63.29% 63% 0 166.67% 100% 3 50% 50% PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS B-K B1O.10 5 100% 5 5 1 B-K B10.20 79 10% 7.9 8 8 B-K B10.30 6 10% 0.6 1 1 Total: 90 14 14 10 ACTUAL ROUND COUNT PERIOD UP 1 20.00% 20% 2 25.32% 25% 1 166.67%

100% 4 28.50% 29%

Revision:

1 Category, ItemNO, HNP-1 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 A HI 1 B11 \C-2 RPV A-I IS1 B1 .I 1 1 B11 \C-2 RPV UPPER SHELL (See RR-38)

AUG 1 Bll OWN PRE B -A HI 1 B11 \C-3 RPV A-1 IS1 81.1 1 1 B11 \C-3 RPV UPPER MIDDLE SHELL (See RR-38)

AUG 1 Bl I OWN PRE B A HI 1 Bll\C-4 RPV A-1 IS1 81.1 1 1 B11 \C-4 RPV LOWER MIDDLE SHELL (See RR-38) AUG 1 Bll OWN PRE B A HI lBlI\C-5 RPV A-1 IS1 81.1 1 1 B11 \C-5 RPV LOWER SHELL (See RR-38) AUG 1 Bll OWN PRE B A HI lBIl\C-1-A ISIIUTI A-1 IS1 81.12 1 B11 \C-1 -A LONG WELD ON UPPER SHELL AUG 1 Bll OWN PRE B -A HI 1 Bll\C-1-B ISIIUTI A-1 IS1 81.12 1 Bll\C-1-B LONG WELD ON UPPER SHELL AUG 1 Bll OWN PRE B -A HI 101 1 \C-1 -C ISllUTl A-1 IS1 81.12 1 B11 \C-1 -C LONG WELD ON UPPER SHELL AUG 1 Bl I OWN PRE B A HI 1 B11 \C-2-A ISIIUTI A-1 IS1 81.12 1 B11 \C-2-A LONG WELD ON UPPER MlDDLE SHELL AUG 1 Bll OWN PRE B -A HI 1 B11\C-2-B ISIIUTI A-l IS1 81.12 1 B11 \C-2-B LONG WELD ON UPPER MIDDLE SHELL AUG 1 Bl I OWN PRE B A HI 1 Bll\C-2-C ISIIUTI A-1 IS1 81 .I2 1 B11 \C-2-C LONG WELD ON UPPER MIDDLE SHELL AUG 1 Bll OWN PRE Page 1 - 5 111 212006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 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 -A HI 1 81 1\C-3-A lSlIUT1 A-1 IS1 81.12 1 81 1 \C-3-A LONG WELD ON LOWER MIDDLE SHELL AUG 1 81 1 OWN PRE LONG WELD ON LOWER MIDDLE SHELL AUG OWN PRE B -A HI 1 81 1\C-3-C lSlIUT1 A-1 IS1 81.12 1 81 1 \C-3-C LONG WELD ON LOWER MIDDLE SHELL AUG 1 81 1 OWN PRE LONG WELD ON LOWER SHELL AUG OWN PRE B -A HI 1 81 1\C-4-8 lSlIUT1 A-1 IS1 81.12 1 81 1 \C-4-8 INACCESSIBLE LONGITUDINAL WELD AUG 1 B11 OWN PRE B -A HI 1811\C-4-C lSlIUT1 A-1 IS1 LONG WELD ON LOWER SHELL AUG OWN PRE B -A HI 1811\C-7 lSlIUT1 A-1 A, 1 -8A-31415 1st 81.21 1 8 1 1 \C-7 HEAD DOME WELD AUG 1 81 1 OWN PRE B -A HI 1811\C-8 A-1 A IS1 81.21 1 81 1 \C-8 INACCESSIBLE AUG 1 81 1 OWN PRE B -A HI 1B1 1\HC-1 ISIIUTI A-2 IS1 81.21 1 81 1 \HC-1 CLOSURE HEAD DOLLAR PLATE WELD AUG 1 81 1 OWN PRE WELD AUG OWN PRE Page 2 - 5 111 212006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 3 - 5 111212006

/ Period 1 Period 2 Period 3 WI. 2 2 5 $ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - . - - - - - - - . - - . . - - - - - - - - - - - . - - - - - - - - - . - . . . - . - - - - - . d UJ 2 2 5 5 ---------s-- - - - - - - - - - - . - .--------s-- - - - - - - - - - - - - ---------S-- - - - - - - - - - - - - ---------s-- - - - - - - . . - . . - ----.----s-- - - - - - - - - - - - - ---------S-- - - - . . . - - - - - - ------.--s-- - - - - - - - - - - - - ----.-.--s-- - - - - - - - - - - - - ---....--s-- - - - - - - . - . . . - .--------s.- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Code Case Class Summary 1 ComplD I System Scope I Method I Procedure B -A HI 1 B1 I\BHD-B ISIIUTI A-1 A, 1-BA-314 IS1 81.22 1 Bll\BHD-B WELD AUG 1 Bll om PRE B -A HI lBlI\BHD-C ISIIUTI A-1 A, 1 -BA-314 IS1 81.22 1 B11 \BHD-C WELD AUG 1 Bl I om PRE B -A HI lBlI\BHD-D ISIIUTI A-1 A, 1 -BA-314 IS1 81.22 1B1 l\BHD-D WELD AUG 1 Bl 1 OWN PRE B -A HI lBlI\BHD-E lSlIUT1 A-1 A, 1 -BA-314 IS1 81.22 I B1 l\BHD-E WELD AUG 1 Bl 1 OWN PRE B -A HI 1B1 l\BHD-F lSlIUT1 A-1 A, 1 -BA-314 IS1 81.22 I B1 l\BHD-F WELD AUG 1 Bl 1 OWN PRE B -A HI 1 B1 l\BHT-A lSlIUT1 A-1 A, 1 -BA-314 IS1 81.22 1 B1 l\BHT-A WELD AUG 1 Bl 1 OWN PRE B -A HI 1B1 l\BHT-B ISIIUTI A-1 A, 1-BA-314 IS1 81.22 1 B11 \BHT-B WELD AUG 1 Bll om PRE B -A HI 1 B1 l\BHT-C ISIIUTI A-1 A, 1 -BA-314 IS1 81.22 1 B11 \BHT-C WELD AUG 1 Bll om PRE B -A HI 1B1 l\BHT-D lSllUT1 A-1 A, 1 -BA-314 IS1 81.22 1 B11 \BHT-D WELD AUG 1 Bl 1 OWN PRE B -A HI 1B1 I\BHT-E lSlIUT1 A-1 A, 1-BA-314 IS1 81.22 1 B11 \BHT-E WELD AUG 1 Bl 1 OWN PRE NO 9 2 2 .T $ - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - . - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - . - - - . - - - - - - . - - - . - - - - - - - - - . . - - - - . . - - . . -

Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 4 - 5 111212006 1 Period 1 Period 2 Period 3 (D I. 2 2 I I - - - - - - - - - - - - - S-- - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - . - - - ------- - - - - - - - - - . - - ------- - - - - . - - - - . . - Category, Iso No. IternNO, Cornp. Desc.

Class Summary 1 CornplD 1 System Scope 1 Method 1 Procedure Code Case B -A HI lBll\BHT-F lSllUT1 A-1 A, 1 -BA-314 IS1 81.22 1 B11 \BHT-F WELD AUG 1 B11 om PRE B -A HI 1 Bl l\BHT-G lSllUT1 A-1 A, 1 -BA-314 IS1 81.22 1 Bl1 \BHT-G WELD AUG 1 B11 om PRE B -A HI 1 B1 l\BHT-H lSllUT1 A-1 A, 1 -BA-314 IS1 81.22 1 B11 \BHT-H WELD AUG 1 B11 om PRE B -A HI lBll\HC-1-A lSllUT1 A-2 IS1 61.22 161 1 \HC-1 -A MERIDIONALWELDCLOSUREHEAD AUG 1 B11 om PRE B -A HI lBll\HC-1-B lSllUT1 A-2 IS1 81.22 I BI 1 \HC-1-B MERIDIONALWELDCLOSUREHEAD AUG 1 B11 om PRE B -A HI 1B1 l\HC-1-C ISIIUTI A-2 IS1 81.22 1 B11 \HC-1 -C MERIDIONALWELDCLOSUREHEAD AUG 1 B11 om PRE B -A HI 1 B1 l\HC-1-D ISIIUTI A-2 IS1 81.22 1 B11 \HC-1-D MERIDIONALWELDCLOSUREHEAD AUG 1 B11 om PRE B -A HI 1 B1 l\HC-1-E ISIIUTI A-2 IS1 81.22 lBll\HC-1-E MERIDIONALWELD CLOSURE HEAD AUG 1 B11 om PRE B -A HI 161 1\HC-1-F ISIIUTI A-2 IS1 81.22 1 B11 \HC-1 -F MERIDIONALWELDCLOSUREHEAD AUG 1 B11 om PRE B -A H1 lBll\HC-1-G ISllUTl A-2 IS1 81.22 1 Bll\HC-1-G MERIDIONALWELDCLOSUREHEAD AUG 1 B11 om PRE NP) m 2 2 L I r r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - . - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - . - - - - - . - ---- - - - - - - - - - . - - --- - - - - . - - - - - - - - - - - - - - - . . . - - - - e V) 2 2 5 5 ---------s-- - - - . - - - - - . - - -------- - - - - - - - - - - - - . - - - - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s----.----- - - - - - - - - - - - - -s--------.. - - - - - - - - - - - - -s---------- - - - - - - - - - - - - s - - . - - - - - - - - - - - - -s - - - - - - - - . - - - .s - - - - - - - - - . - -

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1 HNP-1 Fourth Interval Class 1 IS1 PLan Southern Nuclear Operating Company Page 1 - 6 1/12/2006 1 Period 1 Period 2 Period 3 w h 2 2 r r r I- - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - . - - - - - - - - - - - - - - - - . - - - - . - . - - - - - - . - - - - - - . - - - - - d 10 2 2 5 5 ----------.- . - - - . - - - - - - - ------------ - - - - . - - - - - - - s----------. - - - - - - - - - - - - s----------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - S--.-------- - - - - - - - - - . - - s-------.--- - - - - - - - . . - - - ----s--.---- - - - - - - - - - - . - ----s..----. - - - - . - - - - - - - Category, Iso No.. ItemNO, Cornp. Desc.

Class Summary I CornplD I System Scope I Method 1 Procedure Code Case B -D HI 1B11\N15 (IR) A-1 A IS1 83.100 1 B11 \NI5 (IR) BO'TTOM HEAD DRAIN (Need RR) AUG 1 B11 om PRE B-D HI lBlI\N15(N-SH)

A-1 A IS1 83.90 1 B11 \NI5 (N-SH) BO'TTOM HEAD DRAIN (Need RR) AUG 1 Bll om PRE B-D HI lBll\NlA(IR)

ISllUTlVendor A- 1 IS1 83.100 1 B1 l\NlA (IR) ALOOP RECIRC OUTLETNOZZLE IR AUG 1 B11 om PRE B-D HI 1B1 l\NlA (SH-N) ISIIUTINMP-ES-024-503 A-1 IS1 83.90 1 B1 l\NlA (SH-N) ALOOPRECIRCOUTLETSHELLTONOZ AUG 1 B11 om PRE B-D HI 1 B1 I\NI B (IR) ISIII A- 1 IS1 83.100 1 B11 \N1 B (IR) B LOOP RECIRCOUTLETNOZZLE IR AUG 1 Bll om PRE B -D HI 1 B1 I\N1 B (SH-N) ISIIUTI A- 1 IS1 83.90 1 B11 \N1 B (SH-N) BLOOPRECIRCOUTLETSHELLTONOZAUG 1 B11 OWN PRE B -D H1 1 B11 \N2A (IR) ISllUTlVendor A-l IS1 83.1 00 1 B11 \N2A (IR) B LOOP RECIRC INLET NOZZLE IR AUG 1 B11 om PRE B-D HI 1B11\N2A (N-SH) ISIIUTINMP-ES-024-503 A- 1 IS1 83.90 1 B11 \N2A (N-SH) BLOOPRECIRCINLETNOZZTOSHELL AUG 1 Bll OWN pRE B -D H1 1 B11\N2B (IR) ISIIUTI A-1 IS1 83.100 1 B11\N2B (IR) B LOOP RECIRC INLET NOZZLE IR AUG 1 Bll OWN PRE B -D HI 1 B11\N2B (N-SH) ISIIUTI A-1 IS1 B3.90 1 B11 \N2B (N-SH) B LOOP RECIRC INLETNOZZTO SHELL AUG 1 Bll OWN PRE CY m o 2 2 r r r 7 - - - - - - - . - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - . - - - - - - - - - - - - - -

Revision:

1 HNP-1 Fourth Interval Class 1 IS1 PLan Southern Nuclear Operating Company Page 3 - 6 111212006 1 Period 1 Period 2 Period 3 Category, Iso No. IternNO, Cornp. Desc.

Class Summary I CornplD I System Scope I Method I Procedure Code Case B -D HI 1B11\N2H (IR) ISliUTi A-1 IS1 83.100 1 B11 \N2H (IR) A LOOP RECIRC INLET NOZZLE IR AUG 1 B11 OWN PRE B -D HI 1 B11\N2H (N-SH) ISliUTi A-1 IS1 83.90 1 B11 \N2H (N-SH) ALOOPRECIRCINLETNOZZTOSHELL AUG 1 B11 OWN PRE B-D HI 1 B11\N2J (IR) ISliUTi A-1 , 1 -BF-2 IS1 83.100 1 B11 \N2J (IR) A LOOP RECIRC INLET NOZZLE IR AUG 1 Bl I om PRE HI 1B11\N2J (N-SH) ISliUTi A-1 , 1 -BF-2 IS1 B-D 83.90 1 B11 \N2J (N-SH) A LOOP RECIRC INLETNOZZ TO SHELL AUG 1 Bll OWN PRE B-D HI 1B1 l\N2K(IR)

ISliUTi A- 1 IS1 83.100 1 B11 \N2K (IR) A LOOP RECIRC INLET NOZZLE IR AUG 1 B11 OWN PRE B-D HI 1 B11\N2K (N-SH) ISliUTi A-1 IS1 83.90 1 B11 \N2K (N-SH) ALOOPRECIRC INLETNOZZTOSHELL AUG 1 Bl 1 om PRE B -D HI 1B11\N3A (IR) lSllUT1Vendor A-l IS1 83.100 1 B11 \N3A (IR) A LOOP MS OUTLET NOZZLE IR AUG 1 Bl I OWN PRE B-D HI 1 B11 \N3A (N-SH) ISliUTiNMP-ES-024-503 A- 1 IS1 83.90 1 B11 \N3A (N-SH) ALOOPMSOUTLETSHELLTONOZZ AUG 1 Bl I OWN PRE B-D HI 1 B1 1\N3B (IR) ISliUTiVendor A-l IS1 83.100 1 B11 \N3B (IR) B LOOP MS OUTLET NOZZLE IR AUG 1 Bl I OWN PRE B -D HI 1B11\N3B (N-SH) ISliUTiNMP-ES-024-503 A- 1 IS1 83.90 1 B11 \N3B (N-SH) B LOOP MS OUTLETSHELLTO NOZZ AUG 1 Bl I OWN PRE d V) 2 2 $5 ----s----..- - - - . - - - - - - - - ..--s----.-. - - - - - - - . - - - - ---.-----s-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----s------- - - - - - - - - - - - . ----s------- - - - - - - - . - - - - s.------.--- - - - - - - - - - - . - s-------.--- - - - - - - - . - . - - s------.---- - - . - - - - . - - - . s--.-------. - - - - . . . - . . . - N o m 2 2 5 5 - - - - - - - . . . - . - - - - - - - - - - - . - - - . - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - . . - - . - - - - - - - - - - - . - - - r~ t. 2 2 I I r 7 . . . - - - - - - - - - - - - - - - - - - - - - - - - - . - - - . - - - -s-- - - - - - - - . - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - . . - - - - - - - - - . . - - - . - . - - - - - - - - - - - - . . - - - - -

Revision:

1 HNP-1 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 HI 1B11\N3C (IR) ISIIUTI A-1 IS1 83.100 1 B11\N3C (IR) C LOOP MS OUTLET NOZZLE IR AUG 1 Bll OWN PRE B-D HI 1 B11\N3C (N-SH) ISIIUTI A-1 IS1 83.90 1 B11 \N3C (N-SH) C LOOP MS OUTLET SHELL TO NOZZ AUG 1 Bll OWN PRE B -D HI 1B11\N3D (IR) ISIIUTI A-1 IS1 83.1 00 1 B11 \N3D (IR) D LOOP MS OUTLET NOZZLE IR AUG 1 B11 OWN PRE B-D HI 1 B11\N3D (N-SH) ISIIUTI A-I IS1 83.90 1 B11 \N3D (N-SH) D LOOP MS OUTLET SHELL TO NOZZ AUG 1 Bll OWN PRE B-D HI 1 B1 1\N4A (IR & BORE) ISIIUTlVendor A-1 IS1 83.100 1 B11 \N4A (IR & BORE) A-A LOOP FW INLET NOZZLE IRIBORE AUG 1 Bll OWN PRE B-D HI 1 B11\N4A (N-SH) ISIIUTINMP-ES-024-503 A-1 IS1 83.90 1 B11 \N4A (N-SH) A-A LOOP FW INLET NOZZ TO SHELL AUG 1 Bll OWN PRE B-D HI 1 B11\N4B (IR & BORE) ISIIUTlVendor A-I IS1 83.100 1 B11\N4B (IR & BORE) A-B LOOP FW INLET NOZZLE IRIBORE AUG 1 Bll OWN PRF . ..- B-D HI 1 B11\N4B (N-SH) ISIIUTINMP-ES-024-503 A-1 IS1 83.90 1 B11 \N4B (N-SH) A-B LOOP FW INLET NOZZ TO SHELL AUG 1 Bll OWN PRE B-D HI 1 B11\N4C (IR & BORE) ISllUTIVendor A- 1 IS1 83.100 1 B11\N4C (IR & BORE) B-C LOOP FW INLET NOZZLE IRIBORE AUG 1 Bll OWN PRE B-D HI 1 B11 \N4C (N-SH) ISllUTlNMP-ES-024-503 A-l IS1 83.90 1 B11 \N4C (N-SH) B-C LOOP FW INLET NOZZ TO SHELL AUG 1 Bll OWN PRE Page 4 - 6 111212006 1 Period 1 Period 2 Period 3 (Oh N N E PI Revision:

1 HNP-1 Fourth Interval Class 1 IS1 PLan Southern Nuclear Operating Company Page 5 - 6 1/12/2006 1 Period 1 Period 2 Period 3 63.100 1 B11\N4D (IR & BORE) 1 61 1 6-D LOOP FW INLET NOZZLE IRIBORE AUG ....... ----I----

Category, Iso No. ItemNO, Comp. Desc. Scope 1 Method I Procedure Code Case Class Summary / ComplD 1 System B -D HI 161 1 \N4D (IR & BORE) ISllUTIVendor A-1 IS1 s 2 P1 P1 5 I, s---------.-

N- m 2 2 r r T- T- 83.90 1 B11 \N4D (N-SH) 1 61 1 w h 2 2 5 5 PRE B-D LOOP FW INLET NOZZ TO SHELL AUG ...... OWN ----I----

B-D HI 161 1\N4D (N-SH) ISIIUTINMP-ES-024-503 A-1 IS1 s----------- - - - . PRE B-D HI 161 1\NSA (IR) ISIIUTI A-1 , 1 -6F-5 IS1 63.100 1611\N5A (IR) A LOOP CS INLET NOZZLE IR AUG 1 61 1 OWN PRE B -D HI 1 B11\N5A (N-SH) ISIIUTI A-I , 1-BF-5 IS1 63.90 161 1 \NSA (N-SH) A LOOP CS INLET NOZZ TO SHELL AUG 1 61 1 om PRE B-D HI 161 1\N56 (N-SH) ISIIUTINMP-ES-024-503 A-1 IS1 83.90 1 B11 \NSB (N-SH) B LOOP CS INLET NOZZ TO SHELL AUG 1 61 1 OWN PRE B-D HI 1B11\N6A (IR) ISlll A-2 IS1 63.100 1 B11\N6A (IR) A LOOP RHR HS NOZZLE IR AUG 1 61 1 OWN PRE B -D HI 1 B11 \N6A (N-H) lSl11 A-2 IS1 63.90 1 B11 \N6A (N-H) A LOOP RHR HS NOZZLE TO HEAD AUG 1 61 1 OWN - - - - PRE B-D HI 1B11\N56 (IR) ISllUTIVendor A-1 IS1 63.100 1611\NSB(IR)

B LOOP CS INLET NOZZLE IR AUG 1 61 1 om - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - PRE B-D HI 1611\N66 (IR) lSlIUT1 A-2 IS1 83.100 1 B11\N6B (IR) 6 LOOP RHR HS NOZZLE IR AUG 1 61 1 OWN - - - - ---------s-- - - - - - - - - - - - - - - - - - - - - - - - - PRE B-D HI 1 B11 \N66 (N-H) ISlll A-2 IS1 63.90 1 B11 \N66 (N-H) B LOOP RHR HS NOZZLE TO HEAD AUG 1 61 1 OWN PRE - - - - - - - - - . - - - - - - - S-- - - - - . . - - - - - - s----------- - - - - - - - - - - - . - - - . - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - . . - - . - - - - - ----s-.----- - - - - - - . - - - - - . - - - - - - - . . - - s - - - - - - - - - . - - - - - - - - - . - - - . - - - . - - - - - - -

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

Class Summary 1 CornplD 1 System Scope 1 Method 1 Procedure Code Case B-D HI 1B11\N7 ISI11 A-2 IS1 83.90 1B11\N7 MAIN STEAM VENT NOZZLE AUG 1 Bll OWN PRE B-D HI 1B11\N7 (IR) A-2 IS1 83 100 1 B11 \N7 (IR) MS VENT NOZZLE IR AUG 1 Bll OWN PRE B-D HI 1 B11\N8A (IR) 1SIIUTlVendor A-1 IS1 83.1 00 1 B11 \N8A (IR) A LOOP JET PUMP INSTR NOZZLE IR AUG 1 Bll OWN PRE B-D H1 1 Bl1 \N8A (N-SH) ISIIUTINMP-ES-024-503 A-1 IS1 83.90 1 B11 \N8A (N-SH) SHELL AUG 1 B11 OWN PRE B-D H1 1 B11 \N8B (IR) ISIIUTI A-1 IS1 83.100 1 B11 \N8B (IR) B LOOP JET PUMP INSTR NOZZLE IR AUG 1 B11 OWN PRE B-D H1 1 B1 l\N8B (N-SH) A-1 IS1 83.90 1 Bl1 \N8B (N-SH) SHELL AUG 1 Bll 0 WN PRE B-D HI lB1 l\N9 (IR) ISIIUTlVendor A-1 IS1 83.100 1 B1 l\N9 (IR) CRD INLET NOZZLE IR AUG 1 Bll OWN PRE B-D HI 1 B11 \N9 (N-SH) ISIIUTINMP-ES-024-503 A-1 IS1 83.90 1 Bl 1 \N9 (N-SH) CRD INLET NOZZLE TO SHELL AUG 1 Bll OWN PRE Page 6 - 6 111212006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 - 1 111212006 1 Period 1 Period 2 Period 3 w r. 2 2 x I r - - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Code Case Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure B-F HI 181 1\N15 (N-SE) A-1 A IS1 85.20 1 B11\N15 (N-SE) BOTTOM HEAD DRAIN (RR needed)

AUG 1 Bl I om PRE B-F HI 181 1-1 INST-2A-1 IS111 A-42 IS1 85.20 181 1-1 INST-2A-1 SAFE-END TO PIPE AUG 1 Bl 1 OWN PRE B -F HI 181 1-1 INST-2B-1 A-42 IS1 85.20 1 B11-1 INST-28-1 SAFE-END TO PIPE (Need relief)

AUG 1 B11 om PRE B-F HI 1 C41-1 SBLC-2-1 ISllPTINMP-ES-024301 A-44 IS1 85.20 1 C41-1 SBLC-2-1 END AUG 1 C41 OWN PRE (Y m m 2 2 5 5 - - - - - - - - - - - - - . - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - V) 2 2 I I .? T- ------------ - . - - - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - -

Revision:

1 HNP-1 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-G-1 HI 1 B1 I\NUT-1 IS IIVTI A-2A IS1 B6.10 1 B11 \NUT-1 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI lBIl\NUT-10 A-2A IS1 B6.10 1 B11 \NUT-1 0 CLOSURE HEAD NUT AU G 1 Bl I OWN PRE B-G-1 HI 1B1 l\NUT-11 A-2A IS1 B6.10 1 B11 \NUT-1 1 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI lBIl\NUT-12 A-2A IS1 B6.10 1 B11 \NUT-12 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI 1B1 l\NUT-13 A-2A IS1 B6.10 I B11 \NUT-1 3 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI 1Bl l\NUT-14 A-2A IS1 B6.10 1 B11 \NUT-1 4 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI 1Bl I\NUT-15 A-2A IS1 B6.10 I B1 l\NUT-15 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI lBll\NUT-16 A-2A IS1 B6.10 1 B11 \NUT-16 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI lBIl\NUT-17 A-2A IS1 B6.10 1 B1 l\NUT-17 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE 6-G-I HI 1 B11 \NUT-1 8 A-2A IS1 B6.10 IBll\NUT-18 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE Page I - 25 Period 2 Period 3 Revision:

1 HNP-1 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-G-1 Hl 1 B1 l\NUT-19 A-2A IS1 B6.10 1 B11 \NUT-19 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\NUT-2 A-2A IS1 B6.10 1 B11 \NUT-2 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\NUT-20 A-2A IS1 B6.10 1 B11 \NUT-20 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI 1 B1 l\NUT-21 A-2A IS1 B6.10 1 B11 \NUT-21 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\NUT-22 A-2A IS1 B6.10 1 B11 \NUT-22 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-I HI 1 B1 l\NUT-23 A-2A IS1 B6.10 1 B11 \NUT-23 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\NUT-24 A-2A IS1 CLOSURE HEAD NUT AUG OWN PRE B-G-1 HI 1 Bl l\NUT-25 A-2A IS1 B6.10 1 B11 \NUT-25 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-I HI 1B1 l\NUT-26 A-2A IS1 B6.10 1 B11 \NUT-26 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\NUT-27 A-2A IS1 B6.10 1 B11 \N UT-27 CLOSURE HEAD NUT AUG 1 B11 OWN PRE Page 2 - 25 211 12006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class I 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 BC-1 HI 1B1 l\NUT-28 A-2A IS1 B6.10 1 B11 \NUT-28 CLOSURE HEAD NUT AUG 1 Bll OWN PRE B-G-1 HI 1 B1 l\NUT-29 A-2A IS1 B6.10 1 B11 \NUT-29 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI lBll\NUT-3 A-2A IS1 B6.10 1 B11 \NUT-3 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI 1B1 l\NUT-30 A-2A IS1 B6.10 1 B 1 1

\N UT-30 CLOSURE HEAD NUT AUG 1 Bll OWN PRE B-G-1 HI 1B1 l\NUT-31 A-2A IS1 B6.10 1 B11 \NUT-31 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI 1 Bl l\NUT-32 A-2A IS1 B6.10 1 Bl 1 \NUT-32 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI 1B1 l\NUT-33 A-2A IS1 B6.10 1 Bl 1 \NUT-33 CLOSURE HEAD NUT AUG 1 Bll OWN PRE B-G-1 HI 1B1 l\NUT-34 A-2A IS1 B6.10 1 Bl I \NUT-34 CLOSUREHEADNUT AUG 1 Bl 1 OWN PRE B-G-1 HI 1B1 l\NUT-35 A-2A IS1 B6.10 1 B11 \NUT-35 CLOSURE HEAD NUT AUG 1 B1 1 OWN PRE B-G-1 HI 1B1 l\NUT-36 A-2A IS1 B6.10 1 Bl I \NUT-36 CLOSURE HEAD NUT AUG 1 Bll OWN PRE Page 3 - 25 21112006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 4 - 25 21112006 1 Period 1 Period 2 Period 3 w t. 2 2 I, 5 - - - - - - - - - - - - -s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - . - - - - 3 3 5 5 --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s---------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - .s - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-1 HI 1 B11 \NUT-37 A-2A IS1 B6.10 1 B11 \NUT-37 CLOSURE HEAD NUT AUG 1 B11 om PRE BC-1 HI lB1 l\NUT-38 A-2A IS1 B6.10 1 B11 \NUT-38 CLOSURE HEAD NUT AUG 1 B11 om PRE B-G-1 HI 1 B11 \NUT-39 A-2A IS1 B6.10 1 B11 \NUT-39 CLOSURE HEAD NUT AUG 1 B11 om PRE B-G-1 HI 1 B1 l\NUT-4 A-2A IS1 B6.10 1 B11 \NUT-4 CLOSURE HEAD NUT AUG 1 Bl I OWN PRE B-G-1 HI 1 B1 l\NUT-40 A-2A IS1 B6.10 1 B11 \NUT-40 CLOSURE HEAD NUT AUG 1 B11 om PRE BC-1 HI lBll\NUT-41 A-2A IS1 B6.10 1 B11 \NUT-41 CLOSURE HEAD NUT AUG 1 B11 om PRE B-G-1 HI 1 B1 l\NUT-42 A-2A IS1 B6.10 1 B11 \NUT-42 CLOSURE HEAD NUT AUG 1 B11 om PRE B-G-1 HI 1 B1 l\NUT-43 A-2A IS1 B6.10 1 Bll \NUT-43 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\NUT-44 A-2A IS1 B6.10 1 B11 \NUT44 CLOSURE HEAD NUT AUG 1 B1 1 OWN PRE B-G-1 HI 1 B1 l\NUT-45 A-2A IS1 66.10 161 I \NUT-45 CLOSURE HEAD NUT AUG 1 El 1 om PRE $ E 5 5 - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 5 - 25 2/1/2006 1 Period 1 Period 2 Period 3 (D t- 2 2 5 5 ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----- - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - 5 5 -s - - - - - - - - - - - - ----s------- - - - - - - - - - - - - -s---------- - - - - - - - - -s---------- - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - Category, Iso No. IternNO, Cornp. Desc.

Class Summary I CornplD I System Scope I Method 1 Procedure Code Case B-G-1 HI lBll\NUT-46 A-2A IS1 B6.10 1B11\NUT-46 CLOSURE HEAD NUT AUG 1 B11 om PRE B-G-1 HI 1 B11\NUT-47 A-2A IS1 B6.10 1 B11 \NUT-47 CLOSUREHEADNUT AUG 1 B11 om PRE B-G-1 H1 161 l\NUT-48 A-2A IS1 B6.10 1 B11 \NUT-48 CLOSURE HEAD NUT AUG 1 Bll om PRE B-G-1 HI 181 l\NUT-49 A-2A IS1 B6.10 1 B11 \NUT-49 CLOSURE HEAD NUT AUG 1 61 1 OWN PRE B-G-1 HI 1 B1 l\NUT-5 A-2A IS1 B6.10 1 B11 \NUT-5 CLOSUREHEADNUT AUG 1 B1 1 om PRE B-G-1 H1 161 l\NUT-50 A-2A IS1 B6.10 1 B11 \NUT-50 CLOSURE HEAD NUT AUG 1 61 1 OWN PRE B-G-1 HI 1 B1 l\NUT-51 A-2A IS1 B6.10 1 B11 \NUT-51 CLOSURE HEAD NUT AUG 1 B1 1 OWN PRE B-G-1 H1 1 B1 l\NUT-52 A-2A IS1 B6.10 1 B11\NUT-52 CLOSURE HEAD NUT AUG 1 81 1 OWN PRE B-G-1 HI 161 l\NUT-6 A-2A IS1 B6.10 1 B11 \NUT-6 CLOSURE HEAD NUT AUG 1 81 1 OWN PRE B-G-1 H1 1 B1 l\NUT-7 ISIII A-2A IS1 B6.10 1 B11 \NUT-7 CLOSURE HEAD NUT AUG 1 B11 om PRE 2 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - ----- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - . -

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1 HNP-1 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-G-1 HI 1B1 l\NUT-8 A-2A IS1 B6.10 1 B11 \NUT-8 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\NUT-9 A-2A IS1 B6.10 1 B11 \NUT-9 CLOSURE HEAD NUT AUG 1 B11 OWN PRE B-G-1 HI 1 B31\RC-A PUMP BOLT-1 IS1 86.180 1831 \RC-A PUMP BOLT-1 PUMP BOLTING AUG 1 83 1 OWN PRE B -G -1 HI 1 B31\RC-A PUMP BOLT-10 IS1 86.180 1 B31\RC-A PUMP BOLT-10 PUMP BOLTING AUG 1 83 1 OWN PRE B-G-1 HI 1 B31\RC-A PUMP BOLT-1 1 IS1 86.1 80 1831 \RC-A PUMP BOLT-1 1 PUMP BOLTING AUG 1 83 1 OWN PRE B-G-1 HI 1B31\RC-A PUMP BOLT-12 IS1 86.180 1831 \RC-A PUMP BOLT-1 2 PUMP BOLTING AUG 1 831 OWN PRE B -G -1 HI 1 B31\RC-A PUMP BOLT-13 IS1 86.180 1831 \RC-A PUMP BOLT-1 3 PUMP BOLTING AUG 1 B31 OWN PRE B-G-1 HI 1 B31\RC-A PUMP BOLT-14 IS1 86.180 1 B31\RC-A PUMP BOLT-I4 PUMP BOLTING AUG 1 83 1 OWN PRE B-G-1 HI 1 B31\RC-A PUMP BOLT-15 IS1 86.180 1831 \RC-A PUMP BOLT-15 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 HI 1 B31\RC-A PUMP BOLT-16 IS1 86.180 1 B31\RC-A PUMP BOLT-16 PUMP BOLTING AUG 1 83 1 OWN PRE Page 6 - 25 2/1/2006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 7 - 25 211 12006 1 Period 1 Period 2 Period 3 WL 2 2 3 1, - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - 5 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -----S------ - - - - - - - - - - - - -----S------ - - - - - - - - - - - - Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-1 HI 1 B31\RC-A PUMP BOLT-2 IS1 B6.180 1831 \RC-A PUMP BOLT-2 PUMP BOLTING AUG 1 831 om PRE B-G-I HI 1 B31\RC-A PUMP BOLT-3 IS1 66.180 1 B31\RC-A PUMP BOLT-3 PUMP BOLTING AUG 1 83 1 OWN PRE 6-G-1 HI 1B31\RC-A PUMP BOLT-4 IS1 66.180 1831 \RC-A PUMP BOLT-4 PUMP BOLTING AUG 1 831 om PRE B-G-I HI 1 B31\RC-A PUMP BOLT-5 IS1 86.180 1831 \RC-A PUMP BOLT-5 PUMP BOLTING AuG 1 831 OWN PRE B-G-1 HI 1 B31\RC-A PUMP BOLT-6 IS1 66.180 1831 \RC-A PUMP BOLT-6 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 HI 1 B31\RC-A PUMP BOLT-7 IS1 B6.180 1831 \RC-A PUMP BOLT-7 PUMP BOLTING AUG 1 831 om PRE B-G-1 HI 1 B31\RC-A PUMP BOLT-8 IS1 66.180 1831 \RC-A PUMP BOLT-8 PUMP BOLTING AUG 1 831 OWN PRE B-G-I HI 1 B31\RC-A PUMP BOLT-9 IS1 66.180 1 831 \RC-A PUMP BOLT-9 PUMP BOLTING AUG 1 831 om PRE B-G-1 HI 1B31\RC-B PUMP BOLT-1 lSllUTl IS1 B6.180 1 B31\RC-B PUMP BOLT-1 PUMP BOLTING AUG 1 83 1 OWN PRE B-G-1 HI 1 B31\RC-B PUMP BOLT-10 ISlll IS1 66.1 80 1831 \RC-B PUMP BOLT-1 0 PUMP BOLTING AUG 1 83 1 OWN PRE 2 c9 2 2 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Period 1 Category, Iso No. IternNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-1 H1 1 B31\RC-B PUMP BOLT-1 1 ISlll IS1 B6.180 1 B31\RC-B PUMP BOLT-1 1 PUMP BOLTING AUG 1 831 OWN PRE B-G-I H1 1 B31\RC-B PUMP BOLT-12 ISlll IS1 B6.180 1831 \RC-B PUMP BOLT-1 2 PUMP BOLTING AUG 1 831 OWN PRE . . .- B-G-1 HI 1B31\RC-B PUMP BOLT-13 ISlll IS1 B6.180 1831 \RC-B PUMP BOLT-1 3 PUMP BOLTING AUG 1 831 OWN PRE B-G-I H1 1B31\RC-B PUMP BOLT-14 ISlll IS1 86.1 80 1 B31 \RC-B PUMP BOLT-1 4 PUMP BOLTING AUG 1 831 OWN PRF . . .- B-G-I H1 1 B31\RC-B PUMP BOLT-15 ISlll IS1 B6.180 1 B31 \RC-B PUMP BOLT-1 5 PUMP BOLTING AUG 1 831 OWN PRE B-G-I H1 1 B31\RC-B PUMP BOLT-16 ISlll IS1 86.180 1831 \RC-B PUMP BOLT-1 6 PUMP BOLTING AUG 1 83 1 OWN PRE B-G-I HI 1 B31\RC-B PUMP BOLT-2 ISlll IS1 B6.180 1831 \RC-B PUMP BOLT-2 PUMP BOLTING AUG 1 83 1 OWN PRE . . .- B-G-I HI 1B31\RC-B PUMP BOLT-3 ISlll IS1 86.180 I B31 \RC-B PUMP BOLT-3 PUMP BOLTING AUG 1 831 OWN PRE B-G-I Hl 1 B31\RC-B PUMP BOLT-4 ISlll IS1 86.180 1 B31\RC-B PUMP BOLT-4 PUMP BOLTING AUG 1 83 1 OWN PRE B-G-I HI 1831 \RC-B PUMP BOLT-5 ISlll IS1 86.180 1831 \RC-B PUMP BOLT-5 PUMP BOLTING AUG 1 83 1 OWN PRE Page 8 - 25 211 12006 1 Period 2 Period 3 Revision:

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

/ ComplD / System Scope / Method I Procedure Code Case B-G-1 HI 1 B31\RC-B PUMP BOLT-6 ISlll IS1 B6.180 1831 \RC-B PUMP BOLT-6 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 HI 1B31\RC-B PUMP BOLT-7 lSl// IS1 B6.180 1831 \RC-B PUMP BOLT-7 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 HI lB31\RC-B PUMP BOLT-8 ISIII IS1 B6.180 1831 \RC-B PUMP BOLT-8 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 HI 1 B31\RC-B PUMP BOLT-9 lSl// IS1 B6.180 1831 \RC-B PUMP BOLT-9 PUMP BOLTING AUG 1 831 OWN PRE B-G-1 HI 1 B31\RC-A PUMP-FLANGE ISIIVTINMP-ES-024-201 A-20 IS1 B6.190 1831 \RC-A PUMP-FLANGE FLANGE SURFACE IF DISASSEMBLED AUG 1 831 OWN PRE B-G-1 HI 1 B31\RC-B PUMP-FLANGE ISIIVTINMP-ES-024-201 A-20 IS1 B6.190 1 B31\RC-B PUMP-FLANGE FLANGE SURFACE IF DISASSEMBLED AUG 1 831 OWN PRE B-G-I HI 1 B1 l\STUD-1 ISIII A-2A IS1 86.20 1 B11 \STUD-1 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-I H1 1B1 l\STUD-10 A-2A IS1 86.20 1 B11 \STUD-10 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-I HI 1 B11 \STUD-1 1 A-2A IS1 86.20 1 B11 \STUD-1 1 CLOSURE HEAD STUD AUG 1 Bll OWN PRE B-G-I H1 1 B1 l\STUD-12 A-2A IS1 B6.20 1 B1 l\STUD-12 CLOSURE HEAD STUD AUG 1 Bll OWN PRE Page 9 - 25 Period 2 Period 3 Revision:

1 HNP-1 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-G-1 H1 1B1 l\STUD-13 A-2A IS1 86.20 1 B11 \STUD-1 3 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI IB1 l\STUD-14 A-2A IS1 B6 20 1 B1 1 \STUD-1 4 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 H1 lBll\STUD-15 A-2A IS1 86.20 1 B1 1 \STUD-1 5 CLOSURE HEAD STUD AUG 1 Bll OWN PRE B-G-1 H1 1B1 l\STUD-16 A-2A IS1 86.20 181 1 \STUD-16 CLOSUREHEADSTUD AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\STUD-17 A-2A IS1 86.20 181 1 \STUD-17 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI lBll\STUD-18 A-2A IS1 86.20 1 B11 \STUD-1 8 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1B1 l\STUD-19 A-2A IS1 86.20 1 B11 \STUD-1 9 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\STUD-2 A-2A IS1 86.20 1 B11 \STUD-2 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\STUD-20 A-2A IS1 86.20 1 B11 \STUD-20 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\STUD-21 A-2A IS1 86.20 1 B11 \STUD-21 CLOSUREHEADSTUD AUG 1 B11 OWN PRE Page 10 - 25 21112006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 11 - 25 Period 1 Period 2 21112006 I Period 3 Category, Iso No. ItemNO, Cornp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-1 H1 1 B11 \STUD-22 A-2A IS1 86.20 1 B11 \STUD-22 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1B1 l\STUD-23 A-2A IS1 86.20 1 B11 \STUD-23 CLOSURE HEAD STUD AUG 1 B11 om PRE B-G-1 HI 1 B11 \STUD-24 A-2A IS1 86.20 1 B11 \STUD-24 CLOSURE HEAD STUD AUG 1 B11 om PRE B-G-1 HI 1 B11 \STUD-25 A-2A ISI 86.20 1 B11 \STUD-25 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \STUD-26 A-2A IS1 86.20 1 B11 \STUD-26 CLOSURE HEAD STUD AUG 1 B11 om PRE B-G-1 H1 1 B11 \STUD-27 A-2A IS1 86.20 1 B11 \STUD-27 CLOSURE HEAD STUD AUG 1 B11 om PRE B-G-1 HI 1 B11 \STUD-28 A-2A IS1 86.20 1 B11 \STUD-28 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \STUD-29 A-2A IS1 86.20 1 B11 \STUD-29 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI lBll\STUD-3 A-2A IS1 86.20 1 Bl1 \STUD-3 CLOSURE HEAD STUD AUG 1 B11 om PRE B-G-1 H1 1 B1 l\STUD-30 A-2A IS1 86.20 1 B 1 1 \STU D-30 CLOSURE HEAD STUD AUG 1 B11 OWN PRE ? 5 - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s-.- - - - - - - - - - - - - 0 2 $ 5 .- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - . - - . w r. 2 2 5 5 s--- - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 12 - 25 2/1/2006 1 Period 1 Period 2 Period 3 wr- 2 2 5 5 s--- - - - - - - - - - - - - S--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - S--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-G-1 HI 1 B1 l\STUD-31 A-2 A IS1 86.20 1 B11 \STUD-31 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-I HI lBll\STUD-32 A-2A IS1 B6.20 1 B11 \STUD-32 CLOSUREHEADSTUD AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \STUD-33 A-2 A IS1 86.20 1 B11 \STUD-33 CLOSURE HEAD STUD AUG 1 'a1 1 OWN PRE B-G-1 HI 1 B11 \STUD-34 A-2A IS1 86.20 1 B11 \STUD-34 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 H1 1 B11 \STUD-35 A-2 A IS1 86.20 1 B11 \STUD-35 CLOSUREHEADSTUD AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \STUD-36 A-2A IS1 86.20 1 B11 \STUD-36 CLOSURE HEAD STUD AUG 1 Bl I OWN PRE B-G-1 HI 1 B11 \STUD-37 A-2 A IS1 86.20 1 Bl 1 \STUD-37 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\STUD-38 A-2A IS1 B6.20 1 B11 \STU D-38 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 181 l\STUD-39 lSlll A-2A IS1 86.20 1 B11 \STU D-39 CLOSURE HEAD STUD AUG 1 B11 OWN PRE B-G-1 HI 1 B1 I\STUD-4 A-2A IS1 86.20 1 B11 \STUD-4 CLOSURE HEAD STUD AUG 1 B11 OWN PRE A 0, 2 2 5 5 ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - d V) 2 2 z 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------S--- - - - - - - - - - - - - --------S--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------S--- - - - - - - - - - - - - --------S--- - - - - - - - - - - . - --------S--- - . - - - - - - - - - -

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1 HNP-1 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-G-1 HI 181 l\STUD-5 A-2A IS1 86.20 1 B11 \STUD-5 CLOSURE HEAD STUD AUG 1 811 OWN PRE B-G-1 H1 1 81 1 \STUD-50 A-2A IS1 86.20 181 1 \STUD-50 CLOSURE HEAD STUD AUG 1 81 1 OWN PRE B-G-1 HI 1811\STUD-51 A-2A IS1 86.20 181 1 \STUD-51 CLOSURE HEAD STUD AUG 1 81 1 OWN P RE B-G-1 HI 1 81 1 \STUD-52 A-2A IS1 86.20 181 1 \STUD-52 CLOSURE HEAD STUD AUG 1 81 1 OWN PRE B-G-1 H1 181 l\STUD-6 A-2A IS1 86.20 1 81 1 \STUD-6 CLOSURE HEAD STUD AUG 1 81 1 OWN PRE B-G-1 HI 181 l\STUD-7 A-2A IS1 86.20 1 B11 \STUD-7 CLOSURE HEAD STUD AUG 1 81 1 OWN PRE B-G-1 HI 181 1 \STUD-8 A-2A IS1 86.20 181 l\STUD-8 CLOSUREHEADSTUD AUG 1 81 1 OWN PRE B-G-1 HI 181 l\STUD-9 A-2A IS\ 86.20 181 1 \STUD-9 CLOSURE HEAD STUD AUG 1 81 1 OWN PRE B-G-1 WASHERS ISINTINMP-ES-024201 A-20 IS1 86.200 1831 \RC-A PUMP-NUTS AND WASHERS RC PUMP A NUTS AND WASHERS AUG 1 OWN PRE B-G-1 WASHERS ISIIVTINMP-ES-024-201 A-20 IS1 86.200 1 831\RC-8 PUMP-NUTS AND WASHERS RC PUMP 8 NUTS AND WASHERS AUG 1 831 OWN PRE Page 14 - 25 Period 1 Period 2 Period 3 Revision:

1 Category, ItemNO, HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary / ComplD /System Scope 1 Method I Procedure Code Case B-G-1 HI 1B1 l\LIG-1 ISlll A-2A IS1 FLANGE LIGAMENT AUG OWN PRE A-2A FLANGE LIGAMENT IS1 AUG OWN PRE B-G-1 HI 1B1 l\LIG-11 ISlll A-2A IS1 86.40 1 B11 \LIG-11 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI IB1 l\LIG-12 ISlll A-2A IS1 86.40 1 B11 \LIG-12 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \LIG-13 ISIII A-2A IS1 86.40 1 Bl1 \LIG-13 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI lB1 l\LIG-14 ISIII A-2A IS1 86.40 1 B11 \LIG-14 FLANGE LIGAMENT AUG 1 *31 1 OWN PRE B-G-1 HI 1B1 l\LIG-15 lSl// A-2A IS1 86.40 1 B11 \LIG-15 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1B1 l\LIG-16 lSl// A-2A IS1 86.40 lBll\LIG-16 FLANGE LIGAMENT AUG 1 *31 1 OWN PRE B-G-1 HI lB1 l\LIG-17 IS111 A-2A IS1 86.40 101 1 \LIG-17 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1B1 l\LIG-18 ISIII A-2A IS1 86.40 1 B11 \LIG-18 FLANGE LIGAMENT AUG 1 *31 1 OWN PRE Page 15 - 25 21112006 1 Period 1 Period 2 Period 3 Revision:

I HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD I System Scope I Method I Procedure Code Case B-G-1 Hl 1B1 l\LIG-19 ISIII A-2A IS1 86.40 1 B11 \LIG-19 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 H1 1B1 l\LIG-2 ISIII A-2A IS1 86.40 1 B11 \LIG-2 FLANGE LIGAMENT AUG 1 a1 1 OWN PRE B-G-1 HI 101 1 \LIG-20 ISIII A-2A IS1 86.40 1 B11 \LIG-20 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \LIG-21 IS 111 A-2A IS1 86.40 1 B11 \LIG-21 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \LIG-22 ISI11 A-2A IS1 86.40 1 B11 \LIG-22 FLANGE LIGAMENT AUG 1 Bll OWN PRE B-G-1 H1 lBll\LIG-23 ISlll A-2A IS1 86.40 1 B11 \LIG-23 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI IBll\LIG-24 ISIIl A-2A IS1 86.40 1 B11 \LIG-24 FLANGE LIGAMENT AUG 1 Bl 1 OWN PRE B-G-1 HI 1 81 l\LIG-25 A-2A IS1 86.40 1 B11 \LIG-25 FLANGE LIGAMENT AUG 1 B11 OWN PRE 6-G-1 HI lBll\LIG-26 A-2A IS1 86.40 1 B11 \LIG-26 FLANGE LIGAMENT AUG 1 B11 OWN PRE B -G-1 HI lBll\LIG-27 A-2A IS1 B6.40 1 B11 \LIG-27 FLANGE LIGAMENT AUG 1 B11 OWN PRE Page 16 - 25 21112006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 17 - 25 2H12006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Class Summary / ComplD 1 System Scope 1 Method / Procedure Code Case 6-G-1 HI 1B1 l\LIG-28 A-2A IS1 86.40 1 B11 \LIG-28 FLANGE LIGAMENT AUG 1 Bl I om PRE 6-G-1 HI 1 B11 \LIG-29 A-2A IS1 86.40 1 B11 \LIG-29 FLANGE LIGAMENT AUG 1 B11 om PRE 6-G-1 HI 1 B1 l\LIG-3 ISIII A-2A IS1 86.40 1 B1 I \LIG-3 FLANGE LIGAMENT AUG 1 B11 om PRE 6-G-1 HI I B1 l\LIG-30 A-2A IS1 86.40 1 B11 \LIG-30 FLANGE LIGAMENT AUG 1 B11 OWN PRE 6-G-1 H1 1 B1 l\LIG-31 A-2A IS1 86.40 1 B11 \LIG-31 FLANGE LIGAMENT AUG 1 B11 om PRE 6-G-1 H1 1 B1 l\LIG-32 A-2A IS1 86.40 1 B11 \LIG-32 FLANGE LIGAMENT AUG 1 B11 om PRE B-G-1 HI 1B1 l\LIG-33 A-2A IS1 86.40 1 B11 \LIG-33 FLANGE LIGAMENT AUG 1 B11 om PRE B-G-1 HI 1B1 l\LIG-34 A-2A IS1 86.40 1 B11 \LIG-34 FLANGE LIGAMENT AUG 1 B11 OWN PRE 6-G-1 H1 IBll\LIG-35 A-2A IS1 86.40 1 B11 \LIG-35 FLANGE LIGAMENT AUG 1 B11 om PRE B-G-1 HI 1B1 l\LIG-36 A-2A IS1 86.40 1 B11 \LIG-36 FLANGE LIGAMENT AUG 1 Bl I om pRE z % KK 5 5 --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - { i K ,I z - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - w I. 2 2 5 5 - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 18 - 25 2H12006 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-G-I HI 1B11\LIG-37 A-2A IS1 86.40 1 B 1 1 \LIG-37 FLANGE LIGAMENT AUG 1 Bll OWN pRE B-G-I HI 1 B1 l\LIG-38 A-2A IS1 86.40 1 B11 \LIG-38 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-I HI 181 1 \LIG-39 A-2A IS1 86.40 1 B11 \LIG-39 FLANGE LIGAMENT AUG 1 Bll ow PRE B-G-1 HI 1 B11\LIG-4 ISIII A-2A IS1 86.40 1 B11 \LIG-4 FLANGE LIGAMENT AUG 1 81 1 ow PRE B-G-I HI 1 B1 1\LIG-40 A-2A IS1 86.40 1 B11 \LIG-40 FLANGE LIGAMENT AUG 1 B11 OWN PRE 6-G-I HI 1B1 l\LIG-41 A-2A IS1 86.40 1 B11 \LIG-41 FLANGE LIGAMENT AUG 1 81 1 OWN PRE 6-G-1 HI 1B11\LIG-42 A-2A IS1 B6.40 1 B11 \LIG-42 FLANGE LIGAMENT AUG 1 Bll OWN PRE B-G-I HI 1B11\LIG-43 ISIII A-2A IS1 86.40 1 B11\LIG-43 FLANGE LIGAMENT AUG 1 81 1 ow PRE B-G-1 HI 1 Bl l\LIG-44 ISlli A-2A IS1 86.40 1 B11 \LIG-44 FLANGE LIGAMENT AuG 1 81 1 OWN PRE B-G-I HI 1B11\LIG-45 ISIII A-2A IS1 86.40 1 B11 \LIG-45 FLANGE LIGAMENT AUG 1 Bll ow PRE A 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5 '$ 5 5 --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - . - - - Wb 2 2 5 5 - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - . - - .

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1 HNP-1 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-G-1 HI lBll\LIG-46 ISIII A-2A IS1 86.40 1 B11 \LIG-46 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\LIG-47 ISlll A-2A IS1 86.40 1 B11 \LIG-47 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1B11\LIG-48 ISlll A-2A IS1 86.40 1 B11 \LIG-48 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \LIG-49 ISIII A-2A IS1 B6.40 1 B11 \LIG-49 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 H1 1 B1 l\LIG-5 lSlN A-2A IS1 86.40 1 B11 \LIG-5 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 H 1 1 B11 \LIG-50 ISIII A-2A IS1 86.40 1 B11 \LIG-50 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \LIG-51 ISIII A-2A IS1 B6.40 1 B11 \LIG-51 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1B1 l\LIG-52 ISIII A-2A IS1 86.40 1 B1 l\LIG-52 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \LIG-6 ISllI A-2A IS1 86.40 1 B11 \LIG-6 FLANGE LIGAMENT AUG 1 B11 OWN PRE B-G-1 HI 1 B11 \LIG-7 ISIIl A-2A IS1 86.40 1 B11 \LIG-7 FLANGE LIGAMENT AUG 1 B11 OWN PRE Page 19 - 25 21112006 1 Period 1 Period 2 Period 3 d V) or- .. 12. 2 5 5 ,I Revision:

1 HNP-I Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company Page 20 - 25 21112006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD /System Scope I Method I Procedure Code Case B-G-1 HI 1 B1 l\LIG-8 ISI11 A-2A IS1 B6.40 1 B11 \LIG-8 FLANGE LIGAMENT AUG 1 B11 om PRE B-G-1 HI 101 l\LIG-9 IS I11 A-2A IS1 86.40 1 Bll\LIG-9 FLANGE LIGAMENT AUG 1 B11 om PRE B-G-I HI 101 l\WASHER-1 lSll1 A-2A IS1 86.50 1 B11 \WASHER-1 CLOSURE HEAD WASHER AUG 1 B11 om PRE B-G-1 HI lBll\WASHER-10 ISI11 A-2A IS1 B6.50 1 Bl1 \WASHER-10 CLOSURE HEAD WASHER AUG 1 B11 om PRE B-G-1 HI IBll\WASHER-11 ISI11 A-2A IS1 86.50 1 811 \WASHER-1 1 CLOSURE HEAD WASHER AUG 1 'a1 1 om PRE B-G-1 Hl 1 B1 l\WASHER-12 IS I11 A-2A IS1 B6.50 1 B11 \WASHER-12 CLOSURE HEAD WASHER AUG 1 B11 om pRE B-G-1 HI 1 B1 l\WASHER-13 ISI11 A-2A IS1 86.50 1 B1 l\WASHER-13 CLOSURE HEAD WASHER AUG 1 811 om PRE B-G-1 Hl 1 Bll\WASHER-14 lSlN A-2A IS1 86.50 1 Bll\WASHER-14 CLOSURE HEAD WASHER AUG 1 Bll om pRE B-G-1 HI 1 B11 \WASHER-1 5 ISIII A-2A IS1 B6.50 1 B11 \WASHER-15 CLOSURE HEAD WASHER AUG 1 Bll om PRE B-G-1 HI 1 Bl l\WASHER-16 ISIII A-2A IS1 86.50 1 B11 \WASHER-16 CLOSURE HEAD WASHER AUG 1 Bll OWN PRE 5 $ I, 5 --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - -S---------- - - - - - - - - - - - - -S---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - S - - - - - - - - - - - - - - - ----S------- - - - - - - - - - - - - ----S------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - $ 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - '- - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - . - - - - - 3 $ 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 21 - 25 21112006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD /System Scope / Method / Procedure Code Case B-G-1 Hl 161 l\WASHER-17 lSl// A-2A IS1 66 .SO 101 l\WASHER-17 CLOSURE HEAD WASHER AUG 1 81 1 om PRE B-G-1 HI lBll\WASHER-18 lSl// A-2A IS1 66.50 101 l\WASHER-18 CLOSURE HEAD WASHER AUG 1 Bll oi,AjpJ PRE B-G-1 HI 161 l\WASHER-19 ISIII A-2A IS1 66.50 101 l\WASHER-19 CLOSURE HEAD WASHER AUG 1 61 1 om PRE B-G-1 HI 161 l\WASHER-2 lSl// A-2A IS1 66.50 161 l\WASHER-2 CLOSURE HEAD WASHER AUG 1 61 1 OWN PRE B-G-1 HI 161 l\WASHER-20 lSl// A-2A IS1 66.50 101 l\WASHER-20 CLOSURE HEAD WASHER AUG 1 61 1 om PRE B-G-1 HI 161 l\WASHER-21 lSl// A-2A IS1 86.50 161 1 \WASHER-21 CLOSURE HEAD WASHER AUG 1 61 1 OWN PRE B-G-1 HI 161 l\WASHER-22 lSl// A-2A IS1 66 .SO 1 Bll\WASHER-22 CLOSURE HEAD WASHER AUG 1 61 1 om PRE B-G-1 HI 161 l\WASHER-23 ISlIl A-2A IS1 66 .50 1 Bll\WASHER-23 CLOSURE HEAD WASHER AUG 1 811 OWN PRE B-G-1 HI 161 l\WASHER-24 ISIII A-2A IS1 66.50 101 1 \WASHER-24 CLOSURE HEAD WASHER AUG 1 61 1 OWN PRE B-G-1 HI 161 l\WASHER-25 lSl// A-2A IS1 66 .SO 1 61 1 \WASHER-25 CLOSURE HEAD WASHER AUG 1 61 1 OWN PRE d V, 2 2 5 5 ----s------- - - - - - - - - ----s------- - - - - - - - - ----S------- - - - - - - - - - - - - -S---------- - - - - - - - - - - - - s - - - - - - - - - - - - - - - -s - - - - - - - - - - - - S - - - - - - - - - - - - - - - -s - - - - - - - - - - - - ----S------- - - - - - - - - - - - - - - - - - - - - - - - . . - - - i~ K K ,I 5 - - - - - - - - ------ - - - - - - - - ------ - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - --- - - - - - - - - - - - - --- - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - . - - - - (D b- 2 2 5 5 - - - - - - - - ------ - - - - - - - - ------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 22 - 25 2/1/2006 ( 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-G-1 H1 1 B1 l\WASHER-26 A-2A IS1 B6.50 1 B1 l\WASHER-26 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1B1 l\WASHER-27 A-2A IS1 86.50 1 B11 \WASHER-27 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\WASHER-28 A-2A IS1 B6.50 1 B11 \WASHER-28 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\WASHER-29 A-2A IS1 B6.50 1 B11 \WASHER-29 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1B1 l\WASHER-3 ISIII A-2A IS1 B6.50 1 B11 \WASHER-3 CLOSURE HEAD WASHER AUG 1 Bll OWN PRE B-G-1 HI 1 B1 l\WASHER-30 A-2A IS1 86.50 1 B11 \WASHER-30 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\WASHER-31 A-2A IS1 B6.50 1 B11 \WASHER-31 CLOSURE HEAD WASHER AUG 1 Bll OWN PRE B-G-1 HI 1B1 l\WASHER-32 A-2A IS1 86.50 1 B11 \WASHER-32 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\WASHER-33 A-2A IS1 86.50 1 B11 \WASHER-33 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE 6-G-1 H1 1 B11 \WASHER-34 A-2A IS1 86.50 1 B1 l\WASHER-34 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE Revision:

1 HNP-I Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 23 - 25 21112006 1 Period 1 Period 2 Period 3 Category, lso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope I Method 1 Procedure Code Case B-G-1 HI 1 B1 l\WASHER-35 A-2A IS1 86.50 1 B1 l\WASHER-35 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 H1 1 B1 l\WASHER-36 A-2A IS1 86.50 1 B11 \WASHER-36 CLOSURE HEAD WASHER AUG 1 B11 om PRE B-G-1 HI lB1 l\WASHER-37 A-2A IS1 B6.50 1 B11 \WASHER-37 CLOSURE HEAD WASHER AUG 1 B11 om PRE B-G-1 HI 1 B1 l\WASHER-38 A-2A IS1 86.50 1 B11 \WASHER-38 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\WASHER-39 A-2A IS1 86.50 1 B11 \WASHER-39 CLOSURE HEAD WASHER AUG 1 B11 om PRE B-G-1 HI 1 B1 l\WASHER-4 ISIII A-2A IS1 86.50 1 B11 \WASHER-4 CLOSURE HEAD WASHER AUG 1 B11 om PRE B-G-1 HI 1B1 I\WASHER-40 A-2A IS1 86.50 1 B11 \WASHER-40 CLOSURE HEAD WASHER AUG 1 B11 om PRE B-G-1 HI 161 l\WASHER-41 A-2A IS1 B6.50 1 B11 \WASHER-41 CLOSURE HEAD WASHER AUG 1 B1 1 om PRE B-G-1 HI 1B1 l\WASHER-42 A-2A IS1 86.50 1 Bl l\WASHER-42 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\WASHER-43 ISIII A-2A IS1 86.50 1 B1 l\WASHER-43 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE 5 5 - - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s---------- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - - - - - - - - - - . - - - - - S . - - - - - - - - - - - - - - (1 2 2 5 5 ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - w h g 2 5 5 s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - . - - - - . -

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1 HNP-1 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 / Method I Procedure Code Case B-G-I HI 1 B1 l\WASHER-44 ISIII A-2A IS1 B6.50 1 B11 \WASHER-44 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-I HI 1B1 l\WASHER-45 lSl// A-2A IS1 B6.50 1 B11 \WASHER-45 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-I HI 1 B1 l\WASHER-46 lSl// A-2A IS1 B6.50 1 B1 1 \WASHER-46 CLOSUREHEADWASHER AUG 1 B11 OWN PRE B-G-I HI 1 B1 l\WASHER-47 ISlll A-2A IS1 B6.50 1 B11 \WASHER-47 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B -G-I HI 1B1 l\WASHER-48 ISIII A-2A IS1 86.50 1 El1 \WASHER-48 CLOSURE HEAD WASHER AUG 1 B1 1 OWN PRE B-G-I HI 1 B11 \WASHER-49 IS111 A-2A IS1 86.50 1 B11 \WASHER49 CLOSURE HEAD WASHER AUG 1 B1 1 OWN PRE B-G-I HI 1 B1 l\WASHER-5 ISIII A-2A IS1 86.50 1 B11 \WASHER-5 CLOSURE HEAD WASHER AUG 1 B1 1 OWN PRE B-G-I HI 1 B1 l\WASHER-50 ISIII A-2A IS1 86.50 1 B11 \WASHERdO CLOSURE HEAD WASHER AUG 1 Bl 1 OWN PRE B-G-I H1 1 B1 l\WASHER-51 ISlll A-2A IS1 86.50 1 B1 1 \WASHER-51 CLOSURE HEAD WASHER AUG 1 Bl 1 OWN PRE B-G-I H1 1 B1 l\WASHER-52 ISIII A-2A IS1 B6.50 1 B1 1 \WASHER-52 CLOSURE HEAD WASHER AUG 1 Bl 1 OWN PRE 'age 24 - 25 2/1/2006 1 Period 2 Period 3 Revision:

1 HNP-1 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-G-1 HI 1 B1 l\WASHER-6 lSlll A-2A IS1 86.50 1 B11 \WASHER-6 CLOSURE HEAD WASHER AUG 1 B11 OWN PRE B-G-1 HI 1 B1 l\WASHER-7 lSlll A-2A IS1 86.50 1 B11 \WASHER-7 CLOSURE HEAD WASHER AUG 1 Bll OWN PRE B-G-1 H1 lBll\WASHER8 lSlll A-2A IS1 B6.50 101 1 \WASHER-8 CLOSURE HEAD WASHER AUG 1 Bll OWN PRE B-G-1 HI 1 B1 l\WASHER-9 lSlll A-2A IS1 B6.50 1 B11 \WASHER-9 CLOSURE HEAD WASHER AUG 1 Bll OWN PRE B-G-1 HI 1 B1 l\BUSHING-32 lSlll A-2A, 1-BG-112 IS1 86.508 1 B1 1 \BUSHING-32 CLOSURE HEAD BUSHING AUG 1 Bll OWN PRE B-G-1 HI 1 B11 \BUSHING-33 lSlll A-2A, 1 -BG-1 I2 IS1 86.508 1 B11 \BUSHING-33 CLOSURE HEAD BUSHING AUG 1 Bll OWN PRE B-G-1 HI 1 B1 l\BUSHING-34 lSlll A-2A, 1 -BG-112 IS1 86.508 101 l\BUSHING-34 CLOSURE HEAD BUSHING AUG 1 Bll OWN PRE B-G-1 HI 1 B1 l\BUSHING-35 ISIII A-2A, 1 -BG-1 I2 IS1 86.508 1 Bl 1 \BUSHING-35 CLOSURE HEAD BUSHING AUG 1 Bll OWN PRE Page 25 - 25 21112006 I Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 - 2 111212006 1 Period 1 Period 2 Period 3 W h 2 2 I I r - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - - - - - - - . - - . - - - - - - - V) 2 2 I r r T s----------- - - - - - - - - - - - - s.---------- - - - - - - - - - - - - s----------- - . - - - - - - - - - - s----------- - - - - - - - - - - - - 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-2 HI 1B21-1 CHSV-1FB ISIII A-3 IS1 87.50 1 B21-1 CHSV-1 FB N7 FB IF DISASSEMBLED AUG 1 82 1 OWN PRE B-G-2 HI 1821-1 MS-8A-ASR-2FB ISIIVTINMP-ES-024-201 A-4 IS1 87.50 1821 -1 MS-8A-ASR-2FB 821-F013B FB IF DISASSEMBLED AUG 1 821 ol&N PRE B-G-2 H1 1821-1 MS-8A-BSR-2FB ISIIVTINMP-ES-024201 A-4 IS1 87.50 1821-1 MS-8A-BSR-2FB B21-F013A FB IF DISASSEMBLED AUG 1 821 OWN PRE B-G9 H1 1821-1 MS-80-ASR-2FB ISIIVTINMP-ES-024201 A-5 IS1 87.50 1 021 -1 MS-8B-ASR-2FB B21-F013K FB IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 H1 1821-1 MS-80-BSR-2FB ISIIVTINMP-ES-024-201 A-5 IS1 07.50 1 821 -1 MS-88-BSR-2FB 821-F013D FB IF DISASSEMBLED AUG 1 821 ol&N PRE B-G-2 HI 1821-1 MS-80-CSR-2FB lSl11 A-5 IS1 87.50 1 B21 -lMS-8B-CSR-2FB 821-F013C FB IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1821-1 MS-80-DSR-2FB ISIIVTINMP-ES-024201 A-5 IS1 87.50 1821 -lMS-8B-DSR-2FB 821-F013E FB IF DISASSEMBLED AUG 1 821 OWN PRE 6-G-2 HI 1821 -1 MS-8C-ASR-2FB ISllVTINMP-ES-024-201 A-6 IS1 87.50 1 B21 -lMS-8C-ASR-2FB B21-F013L FB IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1821 -1 MS-8C-BSR-2FB l S Ill A-6 IS1 87.50 1 821 -1 MS-8C-BSR-2FB 821-F013G FB IF DISASSEMBLED AUG 1 821 ol&N PRE B-G-2 HI 1821-1 MS-8C-CSR-2FB ISIIVTINMP-ES-024-201 A-6 IS1 87.50 1821 -1 MS-8C-CSR-2FB 821-F013F FB IF DISASSEMBLED AUG 1 821 OWN PRE m (Y P3 2 2 I I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - . - - - - . - - - - . - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Page 2 - 2 1/12/2006 1 Southern Nuclear Operating Company 1 Period 1 Period 2 Period 3 Category, Iso No. rn N (3 ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope 1 Method I Procedure Code Case 2 2 I I B-G-2 HI 1621-1 MS-8D-ASR-2FB ISIII A-7 IS1 s.-- 87.50 1821 -1 MS-8D-ASR-2FB B21-F013J FB IF DISASSEMBLED AUG - - - - OWN B-G-2 HI 1821-1 MS-BD-BSR-~FB ISINTiNMP-ES-024-201 A-7 IS1 87.50 1821 -1MS-8D-BSR-2FB 821 -F013H FB IF DISASSEMBLED AUG 1 82 1 OWN PRE B-G-2 HI 1831-1 RC-6A-1 FB ISIIVTINMP-ES-024201 A-14 IS1 87.50 1031 -1 RC-6A-1 FB FB IF DISASSEMBLED AUG 1 831 OWN PRE B-G-2 HI 1831-1 RC-60-1 FB ISIIVTINMP-ES-024201 A-15 IS1 s - - - - - - - 87.50 1831-1 RC-68-1 FB FB IF DISASSEMBLED AUG - - - - - - - - 1 831 OWN PRE B-G-2 HI 1 El 1-1 RHR-9A-HS-1 FB ISIIVTINMP-ES-024-201 A-25 IS1 N6A FB IF DISASSEMBLED AUG OWN PRE - - - - - - - - - - - - - - - - - - - - s - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - B-G-2 HI 1 El 1-1 RHR-90-HS-1 FB ISIIVTINMP-ES-024201 A-25 IS1 87.50 1 El 1-1 RHR-9B-HS-1 FB N6B FB IF DISASSEMBLED AUG 1 El 1 om PRE B-G-2 HI 1 E41-1 HPCI-3-R-I FB ISIIVTINMP-ES-024-201 A-29A IS1 87.50 1 E41-1 HPCI-3-R-I FB G31-F203 FB IF DISASSEMBLED AUG 1 E41 OWN - - - - - - - - - - - - s - - - - - - - - - - - - - - - s - - - - - - - - - - -

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7 Category, IternNO. HNP-1 Fourth Interval Class 1 IS\ Plan Southern Nuclear Operating Company lso No. Cornp. Desc. Class Surnrnarv I CornolD / Svstern Sco~e I Method I Procedure code Case - -. . . . . . - . , - ---- r-- B -G -2 H1 1821-F010A Bolting ISllVTlNMP-ES-024201 A-8 IS1 - B7.70GRl 1821 -F010A Bolting GR 1 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1821-F010B Bolting ISIIVTINMP-ES-024201 A-9 IS1 B7.70GRl 1821-F010B Bolting GR 1 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B -G -2 HI 1 B21 -F032A Bolting ISIIVTINMP-ES-024201 A-8 IS1 B7.70GRl 1 821 -F032A Bolting GR 1 VB EXAMINE IF DISASSEMBLED AUG 1 82 1 OWN PRE B-G-2 HI 1821-F032B Bolting ISllVTlNMP-ES-024201 A-9 IS1 B7.70GRl 1821 -F032B Bolting GR 1 VB EXAMINE IF DISASSEMBLED AUG 1 82 1 OWN PRE B-G-2 HI 1 El 1 -F060A Bolting ISllVTlNMP-ES-024-201 A-21 IS1 B7.70GR10 1 El 1 -F060A Bolting GR 10 VB EXAMINE IF DISASSEMBLED AUG 1 El 1 OWN PRE B -G-2 HI 1 El 1 -F060B Bolting ISIIVTINMP-ES-024201 A-22 IS1 B7.70GR10 1 El 1 -F060B Bolting GR 10 VB EXAMINE IF DISASSEMBLED AUG 1 El I OWN PRE 6-G-2 HI 1 E21 -F004A Bolting ISllVTINMP-ES-024201 A-26 IS1 B7.70GRll 1 E21 -F004A Bolting GR 11 VB EXAMINE IF DISASSEMBLED AUG 1 E21 OWN PRE B -G-2 H1 1 E21-F004B Bolting ISIIVTINMP-ES-024201 A-27 IS1 B7.70GR11 1 E21 -F004B Bolting GR 11 VB EXAMINE IF DISASSEMBLED AUG 1 E21 OWN PRE B-G-2 HI 1 E21-FOOSA Bolting ISIIVTINMP-ES-024201 A-26 IS1 B7.70GR11 1 E21 -FOOSA Bolting GR 11 VB EXAMINE IF DISASSEMBLED AUG 1 E21 OWN PRE B-G-2 H1 1 E21 -F005B Bolting ISIIVTINMP-ES-024201 A-27 IS1 B7.70GR11 1 E21 -FOOSB Bolting GR 11 VB EXAMINE IF DISASSEMBLED AUG 1 E21 OWN PRE Page 1 - 6 111212006 ( Period 1 Period 2 Period 3 Revision:

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

Scope I Method I Procedure Code Case B-G-2 H1 1 E21 -F006A Bolting ISIIVTINMP-ES-024201 A-26 IS1 B7.70GR12 1 E21 -F006A Bolting GR 12 VB EXAMINE IF DISASSEMBLED AUG 1 E2 1 OWN PRE B -G -2 HI 1 E21 -F006B Bolting ISIIVTINMP-ES-024201 A-27 IS1 B7.70GR12 1 E21 -F006B Bolting GR 12 VB EXAMINE IF DISASSEMBLED AUG 1 E21 OWN PRE B-G-2 HI 1 E21 -F007A Bolting ISIIVTINMP-ES-024201 A-26 IS1 B7.70GR13 1 E21 -F007A Bolting GR 13 VB EXAMINE IF DISASSEMBLED AUG 1 E21 0 WN PRE B-G-2 HI 1 E21-F007B Bolting ISIIVTINMP-ES-024201 A-27 IS1 B7.70GR13 1 E21 -F007B Bolting GR 13 VB EXAMINE IF DISASSEMBLED AUG 1 E21 OWN PRE B-G-2 HI 1 E41-F006 Bolting ISIIVTINMP-ES-024201 A-29 IS1 B7.70GR14 1 E41 -F006 Bolting GR 14 VB EXAMINE IF DISASSEMBLED AUG 1 E41 OWN PRE Page 2 - 6 111212006 1 Period 1 Period 2 Period 3 B -G -2 HI 1 E41 -F002 Bolting B7.70GR15 1 E41 -F002 Bolting 1 E41 ISIIVTINMP-ES-024201 A-28 IS1 GR 15VB EXAMINE IF DISASSEMBLED AUG OWN PRF 6-G-2 HI 1 G31-F001 Bolting ISIIVTINMP-ES-024201 A-32 IS1 B7.70GR16 1 G31-F001 Bolting GR 16 VB EXAMINE IF DISASSEMBLED AUG 1 G31 OWN PRE B-G-2 HI 1 G31 -F004 Bolting ISIIVTINMP-ES-024-201 A-32 IS1 B7.70GR16 1 G31-F004 Bolting GR 16 VB EXAMINE IF DISASSEMBLED AUG 1 G31 OWN PRE s--- - - - - - - - - - - - - . . .- B -G -2 HI 1 E41-F003 Bolting ISIIVTINMP-ES-024201 A-28 IS1 B7.70GR15 1 E41 -F003 Bolting GR 15VBEXAMlNE IFDISASSEMBLED AUG 1 E4 1 OWN PRE S--- - - - - - - - - - - - - B -G-2 HI 1 G31 -F027 Bolting ISIIVTINMP-ES-024-201 A-32 IS1 B7.70GR17 1 G31 -F027 Bolting GR 17VB EXAMINE IF DISASSEMBLED AUG 1 G31 OWN PRE S - - - - - - - . - . - - - - - . . - - - - - - - - - - . - . -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 3 - 6 111212006 1 Period 1 Period 2 Period 3 (D h 2 2 X I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - . - - - - - - - - - - - - . - - - - - - Category, Iso No. ItemNO, Comp. Desc. Code Case Class Summary I ComplD I System Scope I Method 1 Procedure B -G -2 HI 1 B21-FOllA Bolting ISllVTINMP-ES-024-201 A-8 IS1 B7.70GR2 1821 -F011A Bolting GR2VBEXAMlNEIFDlSASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1821-F011 B Bolting ISIIVTINMP-ES-024-201 A-9 IS1 B7.70GR2 1821 -F011 B Bolting GR2VBEXAMlNEIFDlSASSEMBLED AUG 1 82 1 ow PRE B-G-2 HI 1821-F013A Bolting ISIIVTINMP-ES-024201 A-4 IS1 B7.70GR3 1821 -F013A Bolting GR3VBEXAMlNEIFDlSASSEMBLED AUG 1 82 1 ow PRE B-G-2 HI 1821-F013B Bolting ISIIVTINMP-ES-024-201 A-4 IS1 B7.70GR3 1 821 -F013B Bolting GR 3VB EXAMINE IF DISASSEMBLED AUG 1 821 ow PRE B-G-2 HI 1821-F013C Bolting ISIIVTINMP-ES-024201 A-5 IS1 B7.70GR3 1821 -F013C Bolting GR3VBEXAMlNEIFDlSASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1821-F013D Bolting ISIIVTINMP-ES-024201 A-5 IS1 B7.70GR3 1821-F013D Bolting GR3VBEXAMlNEIFDlSASSEMBLED AUG 1 821 OWN PRE BC-2 HI 1821-F013E Bolting ISIIVTINM P-ES-024-201 A-5 IS1 B7.70GR3 1 821 -F013E Bolting GR 3VB EXAMINE IFDISASSEMBLED AUG 1 821 OWN pRE B-G-2 HI 1821-F013F Bolting ISllVTINMP-ES-024-201 A-6 IS1 B7.70GR3 1 821 -F013F Bolting GR3VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1821-F013G Bolting ISIIVTINMP-ES-024-201 A-6 IS1 B7.70GR3 1821 -F013G Bolting GR3VBEXAMlNEIFDlSASSEMBLED AUG 1 821 OWN PRE B-G-2 Hl 1821-F013H Bolting IS IIVTINM P-ES-024-201 A-7 IS1 B7.70GR3 1821 -F013H Bolting GR3VBEXAMlNEIFDlSASSEMBLED AUG 1 821 OWN PRE m NO 2 2 5 F - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - . - - - 24% a!K X x s----------- - - - - . - - - - - - - s----------- - - - - - - - - - - - - s---------.- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s----------- - - - - - - - - - - - - s-.--------- - - - - - - - - - - - - s.---------- - - - - - - - - - - - - S-----..-.-- - - - - - - . . - - . -

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

Class Summary I ComplD / System Scope I Method / Procedure Code Case B -G -2 H1 1821-F013J Bolting ISIIVTINMP-ES-024-201 A-7 IS1 B770GR3 1821 -F013J Bolting GR 3 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1021-F013K Bolting ISIIVTINMP-ES-024201 A-5 IS1 B7.70GR3 1821 -F013K Bolting GROUP 3 VALVE BOLTING AUG 1 821 OWN PRE B -G -2 H1 1821 -F013L Bolting ISIIVTINMP-ES-024-201 A-6 IS1 B7.70GR3 1821 -F013L Bolting GR 3 VB EXAMINE IF DISASSEMBLED AUG 1 82 1 OWN PRE B-G-2 H1 1 B21-F022A Bolting ISIIVTINMP-ES-024-201 A-4A IS1 B7.70GR4 1 821 -F022A Bolting GR 4 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 H1 1 821 -F022B Bolting ISIIVTINMP-ES-024-201 A-5A IS1 B7.70GR4 1 821 -F022B Bolting GR 4 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1021-F022C Bolting ISllVTINMP-ES-024-201 A-6A IS1 B7.70GR4 1821 -F022C Bolting GR 4 VB EXAMINE IF DISASSEMBLED AUG 1 82 1 OWN PRE B-G-2 H1 1 B21-F022D Bolting ISllVTINMP-ES-024-201 A-7A IS1 B7.70GR4 1 821 -F022D Bolting GR 4VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B -G -2 HI 1 B21-F028A Bolting ISIIVTINMP-ES-024-201 A-4A IS1 B7.70GR4 1 B21 -F028A Bolting GR 4 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B -G-2 HI 1821-F028B Bolting ISI/VT/NMP-ES-024201 A-5A IS1 B7.70GR4 1821 -F028B Bolting GR 4 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1,521-F028C Bolting ISIIVTINMP-ES-024-201 A-6A IS1 B7.70GR4 1 821 -F028C Bolting GR 4 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE Page 4 - 6 Period 1 Period 2 Period 3 Revision:

1 HNP-1 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-G-2 HI 1821-F028D Bolting ISINTINMP-ES-024-201 A-7A IS1 B7.70GR4 1821 -F028D Bolting GR 4 VB EXAMINE IF DISASSEMBLED AUG 1 821 OWN PRE B-G-2 HI 1631-F023A Bolting ISIIVTINMP-ES-024201 A-14 IS1 B7.70GR5 1831 -F023A Bolting GR 4VB EXAMINE IF DISASSEMBLED AUG 1 831 OWN PRE B -G -2 HI 1831 -F023B Bolting ISllVTINMP-ES-024-201 A-15 IS1 B7.70GR5 1831 -F023B Bolting GR 5 VB EXAMINE IF DISASSEMBLED AUG 1 831 OWN PRE B -G -2 HI 1831 -F031 A Bolting ISIIVTINMP-ES-024-201 A-I 48 IS1 B7.70GR5 1 831 -F031A Bolting GR 5 VB EXAMINE IF DISASSEMBLED AUG 1 83 1 OWN PRE B -G -2 H1 1831 -F031B Bolting ISINTINMP-ES-024-201 A-158 IS1 B7.70GR5 1 831 -F031B Bolting GR 5 VB EXAMINE IF DISASSEMBLED AUG 1 83 1 OWN PRE B-G-2 HI 1 El 1-F008 Bolting ISIIVTINMP-ES-024-201 A-23 IS1 B7.70GR6 1 El 1 -F008 Bolting GR 6 VB EXAMINE IF DISASSEMBLED AUG 1 El 1 OWN PRE B -G -2 HI 1 El 1-F009 Bolting ISIIVTINMP-ES-024-201 A-23 IS1 B7.70GR6 1 El 1 -F009 Bolting GR 6VB EXAMINE IF DISASSEMBLED AUG 1 El 1 OWN PRE B -G -2 HI 1 El 1-F015A Bolting ISllVTlNMP-ES-024201 A-21 IS1 B7.70GR7 1 El 1 -FO15A Bolting GR 7 VB EXAMINE IF DISASSEMBLED AUG 1 El 1 OWN PRE B-G-2 HI 1 El 1-F015B Bolting ISINTINMP-ES-024201 A-22 IS1 B7.70GR7 1 El 1 -FO15B Bolting GR 7 VB EXAMINE IF DISASSEMBLED AUG 1 El 1 OWN PRE B -G -2 HI 1 El 1 -F067 Bolting ISlIVTINMP-ES-024-201 A-23 1st B770GR8 1 El 1 -F067 Bolting GR 8 VB EXAMINE IF DISASSEMBLED AUG 1 El 1 OWN PRE Page 5 - 6 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company Page 6 - 6 1/12/2006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope / Method / Procedure Code Case 6-G-2 HI 1 El 1 -F050A Bolting ISI/VT/NMP-ES-024-201 A-21 IS1 B7.70GR9 1 El 1 -F050A Bolting GR9VBEXAMlNEIFDlSASSEMBLED AUG 1 El 1 om PRE 6-G-2 HI 1 El 1 -F050B Bolting ISI/VT/NMP-ES-024-201 A-22 IS1 B7.70GR9 1 El 1 -F050B Bolting GR9VBEXAMlNEIFDlSASSEMBLED AUG 1 El 1 om PRE m w m 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - 5 r r l- 7 S----------- - - - - - - - - - - . - s----------- - - - - - - - - - - - - (Dl. 2 2 I r Y - - - - - - . - - - - - - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Page 1 - 1 1/12/2006 ( Southern Nuclear Operating Company Period 1 Period 2 Period 3 I B -G -2 HI 161 I\FLANGE BOLTING ISII1 87.80 161 1 \FLANGE BOLTING 1 Bl I Category, Iso No. IternNO, Comp. Desc.

Class Summary 1 CornplD 1 System Scope 1 Method /Procedure Code Case 1 -EN-14-1 IS1 ------ - - - - CRD HOUSING FB EXAMINE IF RE-USED AUG OWN . - - - m NO T- r 2 2 x x d u) 2 2 x I (D r- 7 r 2 2 I I Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 - 35 111212006 1 Period 1 Period 2 Period 3 Category, ItemNO. Iso No. Comp. Desc.

Class Summary / ComplD / System Scope / Method / Procedure Code Case B J HI 1821 -1 CHSV-4-1 A-3 IS1 89.1 1 1821 -1 CHSV-4-1 4" DIA. NOZZLE TO FLANGE AUG 1 821 OWN PRE B J HI 1 821 -1 FW-12AA-1 ISIIUTINMP-ES-024-502 A-10 IS1 89.1 1 1 B21-1 FW-12AA-1 TEE TO ELBOW AUG 1 821 OWN PRE B -J HI 1 B21-1 FW-12AA-10 A-1 0 IS1 89.1 1 1821 -1 FW-12AA-10 ELBOW TO PIPE AUG 1 821 OWN PRE B J HI 1821-1 FW-12AA-11 A-10 IS1 89.1 1 1 821 -1 FW-12AA-11 PIPE TO ELBOW AUG 1 821 OWN PRE B-J HI 1 821-1 FW-12AA-12 A-10 IS1 89.1 1 1 821 -1 FW-12AA-12 ELBOW TO PIPE AUG 1 821 OWN PRE B-J HI 1821-1 FW-12AA-13 A-1 0 IS1 89.1 1 1 821 -1 FW-12AA-13 PIPE TO ELBOW AUG 1 821 0 WN PRE B J HI 1 821-1 FW-12AA-14 A-10 IS1 89.1 1 1 821 -1 FW-12AA-14 ELBOW TO PIPE AUG 1 82 1 OWN PRE B-J HI 1821-1 FW-12AA-15 AUG// A-10 IS1 89.1 1 1821 -1 FW-12AA-15 PIPE TO TRANSITION PIECE AUG 1 82 1 OWN PRE B J HI 1821 -1 FW-12AA-16 A-1 0 IS1 89.1 1 1821 -1 FW-12AA-16 TRANSITION PIECE TO NOZZLE AUG 1 821 OWN PRE B-J HI 1 821-1 FW-12AA-2 A-10 IS1 89.11 1821 -1 FW-12AA-2 ELBOW TO PIPE AUG 1 821 OWN PRE Revision:

1 HNP-1 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 HI 1 821 -1 FW-12AA-3 ISlli A-1 0 IS1 69.1 1 1621 -1 FW-12AA-3 ISIIl PIPE TO ELBOW AUG 1 621 OWN PRE B J HI 1821-1 FW-12AA-4 A-1 0 IS1 89.1 1 1821 -1 FW-12AA-4 ELBOW TO PIPE AUG 1 821 OWN PRE B J H1 1821-1 FW-12AA-5 A-1 0 IS1 891 1 1 821 -1 FW-12AA-5 PIPE TO ELBOW AUG 1 82 1 OWN PRE B-J H1 1 821-1 FW-12AA-6 ISlil A-1 0 IS1 89.1 1 1 821 -1 FW-12AA-6 ISlll ELBOW TO PIPE AUG 1 621 OWN PRE B-J HI 1 821 -1 FW-12AA-7 A-1 0 IS1 89.1 1 1 821-1 FW-12AA-7 PIPE TO ELBOW AUG 1 821 OWN PRE B J HI 1821-1 FW-12AA-8 A-10 IS1 89.1 1 1 821 -1 FW-12AA-8 ELBOW TO PIPE AUG 1 82 1 OWN PRE B-J H1 1821 -1 FW-12AA-9 A-1 0 IS1 89.1 1 1821 -1 FW-12AA-9 PIPE TO ELBOW AUG 1 821 OWN PRE B-J HI 1621-1 FW-12AB-1 A-I 1 IS1 REDUCER TO PlPE AUG OWN PRE B-J HI 1821 -1 FW-12AB-10 A-1 1 IS1 TRANSITION PIECE TO NOZZLE AUG OWN PRE B-J HI 1821-1 FW-12AB-2 A-1 1 IS1 PlPE TO ELBOW AUG OWN PRE Page 2 - 35 111 212006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 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 HI 1 821 -1 FW-I 2AB-3 A-1 I IS1 89.1 1 1 B21-1 FW-12AB-3 ELBOW TO ELBOW AUG 1 821 OWN PRE B-J HI 1821-1 FW-12AB-4 A-I 1 IS1 89.1 1 1 821 -1 FW-12AB-4 ELBOW TO PIPE AUG 1 821 OWN PRE B J HI 1821-1 FW-12AB-5 A-I I IS1 89.1 1 1821 -1 FW-12AB-5 PIPE TO ELBOW AUG 1 821 OWN PRF , ,.- B-J HI 1821-1 FW-12AB-6 A-I I IS1 89.1 1 1 821 -1 FW-12AB-6 ELBOW TO PIPE AUG 1 821 OWN PRE B-J HI 1821 -1 FW-12AB-7 A-I I IS1 89.1 1 1 821 -1 FW-12AB-7 PIPE TO ELBOW AUG 1 821 OWN PRE B J HI 1 821 -1 FW-12AB-8 A-I I IS1 89.11 1 821 -1 FW-12AB-8 ELBOW TO PIPE AUG 1 821 OWN PRE B J H 1 1 821-1 FW-I 2AB-9 A-I 1 IS1 89.1 1 1821 -1 FW-12AB-9 PIPE TO TRANSITION PIECE AUG 1 821 OWN PRE B-J HI 1821 -1 FW-12BC-1 A-I 2 IS1 89.1 1 1 821 -1 FW-128C-1 REDUCER TO PIPE AUG 1 821 OWN PRE B-J HI 1821-1 FW-128C-10 A-12 IS1 89.1 1 1821 -1 FW-128C-10 TRANSITION PIECE TO NOZZLE AUG 1 821 OWN PRE B-J HI 1821-1 FW-128C-2 ISlIl A-12 IS1 89.1 1 1821 -1 FW-128C-2 IS111 PIPE TO ELBOW AUG 1 821 OWN PRE Page 3 - 35 Period 1 Period 2 Period 3 Revision:

1 HNP-I Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 4 - 35 111 212006 / Period 1 Period 2 Period 3 (D t- 2 2 I I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - d Y) 2 2 I I F 7 ------------ - - - - - - - - - - - - --------s--- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - . - - - - - . - --.--------- - - - - - - - - - - - - Category, Iso No. IternNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B J HI 1821-1 FW-12BC-3 A-1 2 IS1 89.1 1 1 821 -1 FW-12BC-3 ELBOW TO ELBOW AUG 1 82 1 OWN PRE B-J HI 1821-1 FW-12BC-4 A-1 2 IS1 89.1 1 1 821 -1 FW-12BC-4 ELBOW TO PIPE AUG 1 82 1 om PRE B-J HI 1821-1 FW-12BC-5 A-1 2 IS1 89.1 1 1821 -1 FW-12BC-5 PIPE TO ELBOW AUG 1 821 om PRE B-J HI 1821-1 FW-12BC-6 A-1 2 IS1 89.11 1 821 -1 FW-12BC-6 ELBOW TO PIPE AUG 1 821 om PRE B-J HI 1821-1 FW-12BC-7 A-1 2 IS1 89.1 1 1821 -1 FW-12BC-7 PIPE TO ELBOW AUG 1 82 1 om PRE B-J HI 1821-1 FW-12BC-8 A-1 2 IS1 89.1 1 1 B21-1 FW-12BC-8 ELBOW TO PIPE AUG 1 82 1 OWN PRE B J HI 1821-1 FW-12BC-9 A-1 2 IS1 89.11 1821-1 FW-12BC-9 PIPE TO TRANSITION PIECE AUG 1 821 OWN PRE B J Hl 1821-1 FW-12BD-1 A-1 3 IS1 89.1 1 1821 -1 FW-12BD-1 TEE TO ELBOW AUG 1 821 om PRE B-J HI 1821-1 FW-12BD-10 A-1 3 IS1 B9.11 1 B21-1 FW-12BD-10 ELBOW TO PIPE AUG 1 821 OWN PRE B J HI 1821-1 FW-12BD-11 A-1 3 IS1 89.1 1 1821 -1 FW-12BD-11 PlPE TO ELBOWTRANSITION PIECE AUG 1 82 1 OWN PRE e4 m P) 2 2 I I 7 7 - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s - - - . - - - - - - . - - - - - - - - - - - - - - . - - - - - - - - - - - - - . . . . - . -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 5 - 35 Ill 212006 ( Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Code Case Class Summary 1 ComplD / System Scope / Method I Procedure B-J Hl 1821-1 FW-12BD-12 A-1 3 IS1 89.1 1 1821 -1 FW-1280-12 ELBOW TO PIPE NOZZLE AUG 1 821 OWN PRE B J HI 1821 -1 FW-12BD-13 A-1 3 IS1 89.1 1 1821 -1 FW-1280-13 PIPE TO ELBOW AUG 1 82 1 OWN PRE B J HI 1821-1 FW-1280-14 A-1 3 IS1 89.1 1 1821 -1 FW-12BD-14 ELBOW TO PIPE AUG 1 821 OWN PRE B J HI 1821-1 FW-12BD-15 lSl// A-1 3 IS1 89.1 1 1821 -1 FW-12613-15 lSl// PIPE TO TRANSITION PIECE AUG 1 821 lSl// OWN TRANSITION PIECE TO NOZZLE 1: wm 9 2 2 r 7 r 7 ---- -- - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - lSl// PRE 1- - - - ISI11 PRE B J HI 1821-1 FW-12BD-2 A-1 3 IS1 89.1 1 1 821 -1 FW-1280-2 ELBOWTO PIPE AUG 1 82 1 OWN PRE B-J HI 1821-1 FW-12BD-3 lSlll A-1 3 IS1 89.1 1 1821 -1 FW-128D-3 lSl// PIPE TO ELBOW AUG 1 821 OWN PRE B-J HI 1821-1 FW-1280-4 A-I 3 IS1 89.1 1 1821 -1 FW-12BD-4 ELBOW TO PIPE AUG 1 821 OWN PRE B-J HI 1821-1 FW-12BD-5 A-1 3 IS1 89.1 1 1 821 -1 FW-12BD-5 PIPE TO ELBOW AUG 1 821 OWN PRE 6-J HI 1821-1 FW-12BD-6 A-13 IS1 89.1 1 1821 -1 FW-12BD-6 ELBOW TO PIPE AUG 1 821 OWN PRE B-J Hl 1821-1 FW-12BD-16 ISI// A-1 3 IS1 -s--

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

Class Summary I ComplD I System Scope I Method I Procedure Code Case 6 J HI 1821-1 FW-12BD-7 A-1 3 IS1 89.11 1821 -1 FW-12BD-7 PIPE TO ELBOW AUG 1 821 OWN PRE B J HI 1821 -1 FW-128D-8 A-1 3 IS1 89.1 1 i 821 -1 FW-I 2BD-8 ELBOWTO PIPE AUG 1 821 OWN PRE B-J HI 1821-1 FW-12BD-9 A-1 3 IS1 89.1 1 1821 -1 FW-12BD-9 PIPE TO ELBOW AUG 1 821 OWN PRE B J HI 1821-1 FW-18A-11 A-8 IS1 89.1 1 1 B21-1 FW-18A-11 ELBOW TO PIPE AUG 1 82 1 OWN PRE B-J HI 1 B21-1 FW-18A-12 A-8 IS1 89.1 1 1821 -1 FW-18A-12 PIPE TO ELBOW AUG 1 821 OWN PRE B J HI 1821 -1 FW-18A-13 A-8 IS1 89.1 1 1 821 -1 FW-18A-13 ELBOW TO VALVE AUG 1 621 OWN PRE B J HI 1 821 -1 FW-18A-14 A-8 IS1 89.11 1 821 -1 FW-18A-14 VALVE TO ELBOW AUG 1 82 1 OWN PRE B-J HI 1821-1 FW-18A-15 ISliUTiNMP-ES-024-502 A-8 IS1 89.1 1 1 821 -1 FW-18A-15 ELBOW TO TEE AUG 1 821 OWN PRE 6-J HI 1821-1 FW-18A-16 A-8 IS1 89.1 1 1821 -1 FW-18A-16 TEE TO REDUCER AUG 1 821 OWN PRE B-J HI 1821-1 FW-18A-5 lSlii A-8 IS1 89.1 1 1 821 -1 FW-I 8A-5 lSlii VALVE TO PIPE AUG 1 821 OWN PRE Page 6 - 35 111 212006 1 Period 1 Period 2 Period 3 Revision:

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

Class Summary I ComplD 1 System Scope I Method I Procedure Code Case B-J HI 1 821-1 FW-18A-6 A-8 IS1 89.1 1 1 821 -1 FW-18A-6 PIPE TO TEE AUG 1 821 OWN PRE B-J HI 1821 -1 FW-18A-7 A-8 IS1 89.1 1 1 821 -1 FW-18A-7 TEE TO FLUED HEAD AUG 1 82 1 OWN PRE B-J HI 1821-1 FW-18A-7A A-8 IS1 89.1 1 1 821 -1 FW-18A-7A FLUED HEAD TO PIPE AUG 1 821 OWN PRE B J HI 1821 -1 FW-18A-8 A-8 IS1 89.1 1 1821 -1 FW-18A-8 PIPE TO VALVE AUG 1 82 1 OWN PRE B-J HI 1821-1 FW-18A-9 A-8 IS1 89.1 1 1821 -1 FW-18A-9 VALVE TO ELBOW AUG 1 821 OWN PRE B-J HI 1821 -1 FW-188-10 A-9 IS1 89.1 1 1 821 -1 FW-188-10 PIPE TO ELBOW AUG 1 82 1 OWN PRF . . .- B-J HI 1821 -1 FW-188-11 A-9 IS1 89.1 1 1 821

-1 FW-188-11 ELBOW TO VALVE AUG 1 821 OWN PRE B-J HI 1821-1 FW-188-12 A-9 IS1 89.11 1821 -1 FW-188-12 VALVE TO ELBOW AUG 1 821 OWN PRE B-J HI 1821-1 FW-188-13 A-9 IS1 89.1 1 1 821 -1 FW-188-13 ELBOW TO TEE AUG 1 821 OWN PRE B-J H1 1821 -1 FW-188-14 A-9 I SI 89.1 1 1821 -1 FW-188-14 TEE TO REDUCER AUG 1 821 OWN PRE Page 7 - 35 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 8 - 35 111 212006 1 Period 1 Period 2 Period 3 w I. 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - . - - . - - - - - - - - - . - - - - - - - - . . . - - - - - - - - . . - - - 5 5 -S.--------. - - - - - - - - - - - - ------------ - - - - - - - - - - - - -S---------- - - - - - - - - - - - . ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -.--S------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - --.-s------- - . - - - - - - . - - . ------------ - - - - - - . - . - . - Category, Iso No. ItemNO, Cornp. Desc. Code Case Class Summary I ComplD I System Scope I Method I Procedure B-J HI 1821-1 FW-188-4 lSl// A-9 IS1 89.1 1 1821 -1 FW-188-4 ISI11 VALVE TO PIPE AUG 1 821 OWN PRE B-J HI 1621-1 FW-188-5 A-9 IS1 89.1 1 1821 -1 FW-186-5 PIPE TO PIPE AUG 1 821 om PRE B-J HI 1621-1 FW-188-SBC ISIII A-9 IS1 89.31 1821 -1 FW-186-56C ISlll PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B J HI 1621-1 FW-186-6 A-9 IS1 89.1 1 1621 -1 FW-188-6 PIPE TO FLUED HEAD AUG 1 821 OWN PRE BJ HI 1821-1 FW-186-6A A-9 IS1 89.1 1 1 821 -1 FW-188-6A FLUED HEAD TO PIPE AUG 1 821 OWN PRE B J HI 1621-1 FW-186-7 A-9 IS1 89.1 1 1621 -1 FW-188-7 PIPE TO VALVE AUG 1 821 OWN PRE B J HI 1621-1 FW-188-8 A-9 IS1 89.1 1 1821 -1 FW-188-8 VALVE TO ELBOW AUG 1 821 OWN PRE B-J H1 1621-1 FW-188-9 A-9 IS1 89.1 1 1 821 -1 FW-188-9 ELBOW TO PIPE AUG 1 821 OWN PRE B-J HI 1821 -1 MS-24A-1 A-4 IS1 89.1 1 1 821 -1 MS-24A-1 NOZZLE TO TRANSITION PIECE AUG 1 821 OWN PRE B-J HI 1821 -1 MS-24A-10 A-4 IS1 89.1 1 1 821 -1 MS-24A-10 ELBOW TO PIPE AUG 1 821 OWN PRE NO m 2 2 I I r 7- - - . - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - . - - . - - - . - - - - - . - - - - - - -

Revision:

1 HNP-1 Fourth Interval Class I IS\ 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 H1 1821-1 MS-24A-11 A-4A IS1 89.1 1 1821 -1 MS-24A-11 PIPE TO PIPE AUG 1 82 1 OWN PRE B J H1 1821-1 MS-24A-12 A-4A IS1 89.11 1 B21-1 MS-24A-12 PIPE TO ELBOW AUG 1 821 OWN PRE B J HI 1821-1 MS-24A-13 A-4A IS1 89.1 1 1821 -1 MS-24A-13 ELBOW TO PIPE AUG 1 82 1 OWN PRE B J Hl 1 821 -1 MS-24A-14 A-4A IS1 89.1 1 1 821 -1 MS-24A-14 PIPE TO ELBOW AUG 1 821 OWN PRE B-J HI 1821-1 MS-24A-15 A-4A IS1 89.1 1 1 821-1 MS-24A-15 ELBOW TO PIPE AUG 1 821 OWN PRE B J HI 1821 -1 MS-24A-16 A-4A IS1 89.1 1 1 821 -1 MS-24A-16 PIPE TO VALVE AUG 1 821 OWN PRE B-J Hl 1 821 -1 MS-24A-17 A-4A IS1 89.11 1821 -1 MS-24A-17 VALVE TO PIPE AUG 1 821 OWN PRE B-J HI 1821 -1 MS-24A-17A A-4A IS1 89.1 1 1 821 -1 MS-24A-17A PIPE TO FLUED HEAD AUG 1 82 1 OWN PRE B J HI 1821-1 MS-24A-18 ISIII A-4A IS1 89.11 1 821

-1 MS-24A-18 ISIII FLUED HEAD TO PIPE AUG 1 821 OWN PR E B-J HI 1821-1 MS-24A-19 A-4A IS1 89.11 1821 -1 MS-24A-19 PIPE TO VALVE AUG 1 821 OWN PRE Page 9 - 35 111 212006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 10 - 35 Period 1 Period 2 111212006 I Period 3 Category, lso No. ItemNO, Comp. Desc.

Scope / Method / Procedure Code Case Class Summary l ComplD 1 System B J HI 1 821 -1 MS-24A-2 ISI/1 A-4 IS1 89.1 1 1 821 -1 MS-24A-2 ISIII TRANSITION PIECE TO PIPE AUG 1 821 OWN PRE B J HI 1821 -1 MS-24A-3 A-4 IS! 89.1 1 1821 -lMS-24A-3 PIPE TO ELBOW AUG 1 821 OWN PRE B J HI 1821 -1 MS-24A-4 A-4 IS1 89.1 1 1 821 -1 MS-24A-4 ELBOW TO PIPE AUG 1 821 OWN PRE B J HI 1821-1 MS-24A-5 A -4 IS1 89.1 1 1 821 -1 MS-24A-5 PIPE TO PIPE AUG 1 821 OWN PRE B-J HI 1821-1 MS-24A-6 A-4 IS1 89.1 1 1 821 -1 MS-24A-6 PIPE TO PIPE AUG 1 821 OWN PRE B-J HI 1821 -1 MS-24A-7 A-4 IS1 89.1 1 1 821 -1 MS-24A-7 PIPE TO ELBOW AUG 1 821 OWN pRE B J HI 1821-1 MS-24A-8 A-4 IS1 89.1 1 1 821 -1 MS-24A-8 ELBOW TO PIPE AUG 1 821 OWN pRE B-J HI 1821 -1 MS-24A-8BC-1 lSl// A-4 IS1 89.31 1821 -lMS-24A-8BC-I lSl/l PIPE TO BRANCH CONNECTION AUG 1 821 OWN pRE B-J HI 1821 -1 MS-24A-8BC-2 ISI/UT/ A-4 IS1 89.31 1821 -1 MS-24A-8BC-2 PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B-J HI 1821-1 MS-24A-9 A -4 IS1 89.1 1 1 821 -1 MS-24A-9 PIPE TO ELBOW AUG 1 821 OWN PRE P Y) 2 2 I I 7- T- -S---------- - - - - - - - - - . - - ------------ - - - - - - - - - - - - ------------ - - - - - - . - - - - - ------------ - - - - - - - - - - - - ---------.-- - - - - - - - - - - - - --.--------- - - - - - - - - - - - - --------s-.- - - - - - - - - - - - - .s---------- . - - - - - - - - - - - - - - - . - - - - - - - - - - . - - . - - . - - - - . - N 01 o 2 2 5 z - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - . - - - - - - - . - - - - . - - . - - - - - ----- - - - - . - - - - - - - wr. 2 2 5 5 - - - - - - - - . - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - . - - - - - - - - - - - -.--.-- . . - . . - . - - - - -

Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 11 - 35 111212006 1 Period 1 Period 2 Period 3 w h 2 2 I I - - - - - - - - - - - - s--- - - - - ------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - . - - - - - - - - - - - - - - - - d Y, 2 2 I I 7- 7 -s---------- - - - - - - - - - - - - - - - - - - - - - - - - s----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - -s---------- - - - - - - - - - - - - ----s------- - - - - - - - - - - - - ------------ - - - - - - . - - - - - ------------ . - - - - - - - - - - - ------------ . - - - - - - . - - - - -s--..------ - . - . - - - - - - - - Category, lso No. ItemNO, Comp. Desc. Code Case Class Summary 1 ComplD I System Scope 1 Method 1 Procedure B-J HI 1821 -1 MS-248-1 IS111 A-5 IS1 B9.11 1 B21-1 MS-248-1 ISIII NOZZLE TO TRANSITION PIECE AUG 1 821 om PRE B-J H1 1821-1 MS-24B-10 A-5 IS1 89.1 1 1821 -lMS-24B-10 PIPE TO ELBOW AUG 1 821 om PRE B J HI 1 B21-1 MS-248-11 ISliUTINMP-ES-024-502 A-5 IS1 B9.11 1 B21-1 MS-248-11 ELBOW TO PIPE AUG 1 82 1 om PRE B J HI 1821-1MS-24B-12 A-5A IS1 89.11 1821 -1 MS-248-12 PIPE TO PIPE AUG 1 821 om PRE B J HI 1 B21-1 MS-248-13 ISlii A-5A IS1 B9.11 1 B21-1 MS-24B-13 ISlli PIPE TO ELBOW AUG 1 821 OWN PRE B J HI 1821 -1 MS-248-14 A-SA IS1 B9.11 1821 -1 MS-248-14 ELBOWTO PIPE AUG 1 821 OWN PRE B-J HI 1 B21-1 MS-24B-15 A-SA IS1 B9.11 1 821 -1 MS-24B-15 PIPE TO VALVE AUG 1 821 OWN PRE B-J H1 1821-1 MS-248-16 A-S A IS1 89.1 1 1 821

-1 MS-248-16 VALVE TO PIPE AUG 1 821 OWN PRE B-J H1 1821 -1 MS-248-16A A-SA IS1 89.1 1 1 821 -1 MS-248-16A PIPE TO FLUED HEAD AUG 1 B21 OWN PRE B-J HI 1 B21-1 MS-24B-17 ISIii A-SA IS1 89.1 1 1 821 -1 MS-24B-17 ISlii FLUED HEAD TO PIPE AUG 1 821 OWN PRE (Y 9 1.3 2 2 I I .- - - - - - - . - - - . - - - - - - - - - ------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - . - . - - - - - - . - - - . - - - - - - - - - - - - - - - - - - . . . - - - - - - - - - . - -

Revision: 1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 12 - 35 111 212006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Scope i Method / Procedure Code Case Class Summary i ComplD 1 System B J HI 1821 -1 MS-248-18 A-5A IS1 89.1 1 1821 -1 MS-248-18 PIPE TO VALVE AUG 1 621 OWN PRE B 4 H1 1821 -1 MS-248-2 A-5 IS! 89.1 1 1 821 -1 MS-248-2 TRANSITION PIECE TO PIPE AUG 1 821 OWN PRE B J HI 1821 -1 MS-24B-3 ISIII A-5 1st 89.1 1 1821 -1 MS-248-3 ISIII PIPE TO ELBOW AUG 1 02 1 OWN PRE B-J HI 1821-1 MS-248-4 A-5 IS1 89.11 1 821 -1 MS-248-4 ELBOW TO PIPE AUG 1 821 OWN PRE B-J HI 1821-1 MS-248-5 A-5 IS1 89.1 1 1 821 -1 MS-248-5 PIPE TO PIPE AIJG 1 82 1 OWN PRE B J H1 1821 -1 MS-248-6 A-5 IS1 89.1 1 1 821 -1 MS-248-6 PIPE TO PIPE AUG 1 82 1 OWN PRE B J HI 1821-1 MS-248-6BC A-5 IS1 89.31 1 821 -1 MS-248-6BC PIPE TO BRANCH CONNECTION AUG 1 82 1 om PRE B J H1 1821 -1 MS-240-7 A-5 IS1 89.1 1 1821 -1 MS-24B-7 PIPE TO ELBOW AUG 1 821 om pRE B J HI 1821-1 MS-248-8 A-5 1st 89.1 1 1 821 -1 MS-24B-8 ELBOW TO PIPE AIJG 1 82 1 OWN pRE B-J HI 1821-1 MS-248-8BC-1 A-5 IS1 89.31 1 821 -1 MS-248-8BC-1 PIPE TO BRANCH CONNECTION AIJG 1 82 1 OWN PRE V) 2 2 5 5 ------------ - - - - . - - - - - - - ------------ - - - - - - - - - . - - -S---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------.--- - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------.--- - - - - - - - - - - - - -------.---- - - - - - - - - - - - - ------------ - - - - - - - - - - - - (Y 4 P) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - . - . - - - - - . - - - . - - - - - - W h 2 2 I 7 I -? - - - - - - - - - - - - - - - - - - . - - . - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - . - - - - - - - - - - . . - . - - - - - - - - - - - - . - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 13 - 35 111212006 1 Period 1 Period 2 Period 3 w h 2 2 5 5 - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - . - - - - - - - - . - . - . - - - - - - - - . - - . 8: a: a .f 5 ------------ - - - - . - . - - - - - ------------ - - - - . - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - . - - - - - - - - - ------------ - - - - - - - - - - . - ------------ - - - - - - - - - - - - -.---------. - - - - - - - - - - . - ------------ - - - - - - - - - . - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B J HI 1821-1 MS-248-8BC-2 A-5 IS1 89.31 1 821 -1 MS-248-8BC-2 PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B J HI 1821-1 MS-248-8BC-3 A-5 IS1 89.31 1821 -1MS-24B-8BC-3 PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B J HI 1821-1 MS-248-88C-4 A-5 IS1 89.31 1821 -1 MS-248-8BC-4 PIPE TO BRANCH CONNECTION AUG 1 82 1 om PRE B-J HI 1821 -1 MS-248-9 A-5 IS1 89.1 1 1821 -1 MS-248-9 PIPE TO PIPE AUG 1 821 OWN PRE B J HI 1821 -1 MS-24C-1 A-6 IS1 89.1 1 1 821 -1 MS-24C-1 NOZZLE TO TRANSITION PIECE AUG 1 821 om PRE B J HI 1821 -1 MS-24C-10 A-6 IS1 89.1 1 1821 -1 MS-24C-10 PIPE TO ELBOW AUG 1 821 om PRE B J HI 1821 -1 MS-24C-11 A-6 IS1 89.1 1 1821 -1 MS-24C-11 ELBOW TO PIPE AUG 1 821 OWN PRE B J HI 1821 -1 MS-24C-12 A-6A IS1 89.1 1 1821 -1 MS-24C-12 PIPE TO PIPE AUG 1 821 om PRE B J HI 1821 -1 MS-24C-13 A-6A IS1 89.1 1 1 821 -1 MS-24C-13 PIPE TO ELBOW AUG 1 821 om PRE B-J HI 1821-1 MS-24C-14 A-6A IS1 89.1 1 1 821 -1 MS-24C-14 ELBOW TO PIPE AUG 1 82 1 om PRE N rn o 2 2 I I - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - . - - - . - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 14 - 35 Period 1 Period 2 111212006 1 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B-J H1 1821-1 MS-24C-15 A-6A IS1 89.1 I I 821 -1 MS-24C-15 PIPE TO VALVE AUG 1 821 om PRE B-J HI 1821 -1 MS-24C-16 A-6A IS1 89.1 1 1821 -1 MS-24C-16 VALVE TO PIPE AUG 1 821 om PRE B J HI 1821 -1 MS-24C-16A A-6A IS1 89.1 1 1 821 -1 MS-24C-16A PIPE TO FLUED HEAD AUG 1 821 om PRE B-J HI 1821 -1 MS-24C-17 A-6A IS1 89.11 1 821

-1 MS-24C-17 FLUED HEAD AUG 1 82 1 om PRE B-J HI 1 821 -1 MS-24C-18 A-6A IS1 89.1 1 1 821 -1 MS-24C-18 PIPE TO PIPE AUG 1 82 1 OWN PRE B J HI 1821 -1 MS-24C-19 A-6A IS1 89.11 1821 -1 MS-24C-19 PIPE TO PIPE AUG 1 821 ow PRE B 4 HI 1 821 -1 MS-24C-2 IS111 A-6 IS1 89.1 1 1 821 -1 MS-24C-2 ISlil TRANSITION PIECE TO PIPE AUG 1 821 om PRE B-J HI 1821 -1 MS-24C-20 IS111 A-6A IS1 89.11 1821 -1 MS-24C-20 ISlii PIPE TO VALVE AUG 1 821 OWN PRE B-J HI 1821 -1 MS-24C-3 A-6 IS1 89.11 I 821 -I MS-24C-3 PIPE TO ELBOW AUG 1 821 OWN PRE B-J HI 1821-1 MS-24C-4 A-6 IS1 89.1 1 1 821 -1 MS-24C-4 ELBOW TO PIPE AUG 1 821 om PRE W h 2 2 E E - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - . - - - - - - - . - - - - - - - . - - - - - - - - - - - 10 N W P 2 r x -? -? - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - A - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - . - - - - . - - - - - - - - - - - . - - . - - - . - - d Y) P P ,I E ----.---s--- - . - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - . - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - . - - - - -s---------- - - - - - - - . - - - - -s------.--- - - - - - - - - - - - - ---------.-. - - - - - - - - - - - - ------------ - - - - - - - - - - - .

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1 HNP-1 Fourth lnterval 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 J H1 1821-1 MS-24C-5 A-6 IS1 89.11 1 821 -1 MS-24C-5 PIPE TO PIPE AUG 1 821 OWN PRE B 4 HI 1821 -1 MS-24C-6 A-6 IS1 89.11 1821 -1 MS-24C-6 PIPE TO PIPE AUG 1 821 OWN PRE 6-J HI 1821-1 MS-24C-7 A-6 IS! 89.1 1 1 821 -1 MS-24C-7 PIPE TO ELBOW AUG 1 821 OWN PRE 6-J HI 1821 -1 MS-24C-8 A-6 IS1 89.1 1 1821 -1 MS-24C-8 ELBOW TO PIPE AUG 1 821 OWN PRE B-J HI 1821 -1 MS-24C-8BC-1 A-6 IS1 89.31 1 821 -1 MS-24C-8BC-1 PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B-J HI 1821-1 MS-24C-8BC-2 A-6 IS1 89.31 1 821 -1 MS-24C-8BC-2 PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B-J HI 1821-1 MS-24C-8BC-3 A-6 IS1 89.31 1 821 -1 MS-24C-8BC-3 PIPE TO BRANCH CONNECTION AUG 1 821 OWN PRE B-J H1 1821 -1 MS-24C-9 A-6 IS1 89.1 1 1 821 -1 MS-24C-9 PIPE TO PIPE AU G 1 821 OWN PRE B-J H1 1821 -1 MS-24D-1 A-7 IS1 89.1 1 1 821 -1 MS-24D-1 NOZZLE TO TRANSITION PIECE AUG 1 821 OWN PRE B-J HI 1821-1 MS-24D-10 A-7 IS1 89.1 1 1821 -lMS-24D-10 ELBOW TO PIPE AUG 1 821 OWN PRE Page 15 - 35 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 16 - 35 Period 1 Period 2 111212006 1 Period 3 A-7A PlPE TO PlPE Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-J HI 1 821 -1 k-24~-12 89.1 1 1821 -1 MS-24D-12 A-7A PlPE TO ELBOW m N rn I I 2 2 PRF 1 - - - - - . 1. . . - 5 2 I r 1 821 OWN PRE B-J HI 1821 -1 MS-24D-13 A-7A IS1 89.11 1821 -1 MS-24D-13 ELBOW TO PIPE AUG 1 821 OWN A-7A PlPE TO ELBOW w h 2 2 I I B-J H1 1821-1 hk-24~-15 89.1 1 1 821 -1 MS-24D - - - - - - - - - - - - - - - A-7A ELBOW TO PlPE - - - - - - - - ------------ - - - - - - - - OWN PRE 1: :I- I---- - - - - - - - - - - - - - - - - - - - - - - - 1 82 1 OWN PRE B J H1 1821-1 MS-24D-16 A-7A IS1 89 11 1 821 -1 MS-24D-16 PIPE TO VALVE AUG B-J HI 1821-1 MS-240-17 A-7A IS1 89.1 1 1821 -1 MS-24D-17 VALVE TO PIPE AUG 1 821 OWN PRE B-J Hl 1 821 -1 MS-240-17A A-7A IS1 89 11 1821 -1 MS-240-17A PIPE TO FLUED HEAD AUG 1 821 OWN PRE B-J HI 1821-1 MS-24D-18 89.11 1 821 -1 MS-24D - - - - - - - - - - - A-7A FLUED HEAD TO PlPE IS1 AUG - - - - . - . - ----s------- - - - - 1 821 OWN PRE B-J HI 1 821 -1 MS-24D-19 A-7A IS1 89 11 1 821 -1 MS-24D-19 PIPE TO VALVE AUG 1 821 OWN PRE - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 17 - 35 111212006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Scope I Method I Procedure Code Case Class Summary 1 ComplD 1 System BJ Hl 1821-1 MS-240-2 A-7 IS1 89.1 1 1821 -1 MS-24D-2 TRANSITION PIECE TO PIPE AUG 1 82 1 OWN PRE B J HI 1821-1 MS-24D-3 A-7 ISI 89.1 1 1 821 -1 MS-24D-3 PIPE TO ELBOW AUG 1 821 OWN PRE B-J HI 1821-1 MS-24D-4 A-7 IS1 89.1 1 1 B21-1 MS-24D-4 ELBOW TO PIPE AUG 1 821 OWN PRE B J H1 1821 -1 MS-24D-5 A-7 IS1 89.1 1 1821 -1 MS-240-5 PIPE TO PIPE AUG 1 821 OWN PRE B-J HI 1821 -1 MS-24D-6 A-7 IS1 89.1 1 1 821 -1 MS-24D-6 PIPE TO PIPE AUG 1 821 OWN PRE B-J Hl 1821-1 MS-24D-7 A-7 IS1 89.1 1 1 B21-1 MS-24D-7 PIPE TO ELBOW AUG 1 021 OWN pRE B-J HI 1821-1 MS-24D-8 A-7 IS1 89.11 1 821-1 MS-24D-8 ELBOW TO PIPE AUG 1 82 1 OWN pRE B J Hl 1821-1 MS-24D-8BC A-7 IS1 89.32 1 B21-1 MS-24D-8BC PIPE TO BC AUG 1 82 1 OWN PRE B-J HI 1821-1 MS-24D-8BC-1 A-7 IS1 89.31 1 B21 -lMS-24D-8BC-1 PIPE TO BRANCH CONNECTION AUG 1 02 1 om PRE B-J HI 1821-1 MS-24D-8BC-2 A-7 IS1 89.31 1 821 -1 MS-24D-8BC-2 PIPE TO BRANCH CONNECTION AUG 1 62 1 OWN PRE 5 5 ------------ - - - . . - - - - - - - ------------ - - - - - . - - - . - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - . - - ------------ - . - - - - - - - - - - --------.--- - - - - - - - - - - . - ---.-----.-- - - . - - - - - - . - - ------------ - - - - . - - - - . - . (Y Q P) 2 2 5 5 - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - . - - - - - - - . - - - . - - - - - - (O h 2 2 I r I l- - - - - - . - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - . - - - - - - - - - - - - - - - . - - - - - - - - - - . . - - - - - - - - - - - - - - . - - .

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 18 - 35 Period 1 Period 2 Period 3 Category, ItemNO, Class Summary I ComplD I System Iso No. Comp. Desc.

Scope I Method I Procedure Code Case B-J HI 1821 -1 MS-24D-9 A-7 IS1 89.1 1 1821 -1 MS-24D-9 PIPE TO ELBOW AUG 1 82 1 OWN PRE B-J HI 1821-1 MS-8A-ASR-1 A-4 IS1 89.1 1 1 821 -1 MS-8A-ASR-1 BRANCH CONNECTION TO PIPE AUG 1 821 OWN PRE B-J HI 1 821 -1 MS-8A-ASR-2 ISIIUTINMP-ES-024-502 A-4 IS1 89.1 1 1 821 -1 MS-8A-ASR-2 PIPE TO FLANGE AUG 1 821 OWN PRE B J H1 1821-1 MS-8A-BSR-1 A-4 IS1 891 1 1821 -1 MS-8A-BSR-1 BRANCH CONNECTION TO PIPE AUG 1 821 OWN PRE A-4 PlPE TO FLANGE IS1 AUG OWN PRE B J HI 1821-1 MS-88-ASR-1 A-5 IS1 BRANCH CONNECTION TO PIPE AUG OWN PRE A-5 PlPE TO FLANGE IS1 AUG 1 821 OWN PRE 8-J HI 1821-1 MS-88-BSR-1 ISIIUTINMP-ES-024-502 A-5 IS1 89.1 1 1821 -1 MS-88-BSR-1 BRANCH CONNECTION TO PIPE AUG 1 82 1 OWN PRE B-J HI 1821-1 MS-88-BSR-2 89.1 1 1821 -1 MS-88-BSR-2 A-5 PIPE TO FLANGE IS1 AUG 1 821 OWN PRE B-J HI 1821 -1 MS-88-CSR-I A-5 IS1 89.1 1 1821 -1 MS-88-CSR-1 BRANCH CONNECTION TO PIPE AUG 1 82 1 OWN PRE 2 r 2 A m a m A Y Z : b z ? ?' R "o ? & A ? - % ?, D Z 0 I 0 o Z Z rn 0 3 0 Z -4 0 2 D rn A g r 2 2 gir 2 - m 2 z N (n: wz 0 cn b m cn 0 ?h N cn N ? L'? D m rn -4 0 n 5 Z GJ rn 2 g 2 2 m m 2 z (n L to K ? ?' 0 a~ cn 0 $ 2 ?J %: 9 Z 0 I 0 o Z Z rn 0 5 0 Z -4 0 n_ D rn - - 2 g r A A --Z YG- 8 m A N 5 : 20 z 0 cn & b %: k (n N ? 0 P D m rn -4 0 n F z GJ rn IIII4IIIIIIIIIIIIIIIIIIII -wm 2 " C 2 --Z zg- I w 2 Y 2 : 20 z 0 cn &, m $2 - cn A ? %: D Z 0 I 0 o Z Z rn 0 5 0 Z -4 0 2 D rn IIIIIIIIIIIJIIII4II,IIIIII,II,I,II IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIJIIIIII,, IIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIIII IIII~IIIIIIIIIIIJIIIIIIIJIIIIIIIIIIIIIII IIIIIIIIIIIIIIIIIIIIIIIIIIIIJIIIIII

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

Scope I Method I Procedure Code Case B J HI 1821-1 MS-8D-ASR-2 A-7 IS1 89.1 1 1 821 -1 MS-8D-ASR-2 PIPE TO FLANGE AUG 1 821 OWN PRE B J HI 1821-1 MS-8D-BSR-1 A-7 IS1 89.1 1 1821 -1 MS-8D-BSR-1 BRANCH CONNECTION TO PIPE AUG 1 821 OWN PRE B J HI 1821-1 MS-8D-BSR-2 A-7 IS1 PlPE TO FLANGE AUG OWN PRE B-J HI 1 El 1-1 RHR-208-D-10 A-23 IS1 89.1 1 1 El 1-1 RHR-208-D-10 PIPE TO PIPE AUG 1 El 1 OWN PRE B J HI 1 El 1-1 RHR-208-D-IOA A-23 IS1 89.1 1 1 El 1-IRHR-208-D-1OA PIPE TO PIPE AUG 1 El 1 OWN PRE B J HI 1El1-1 RHR-208-D-11 ISllUTl A-23 IS1 89.1 1 1 El 1-1 RHR-20B-D-11 PIPE TO VALVE AUG 1 El I OWN PRE B J HI 1 El 1-1 RHR-208-D-12 A-23 IS1 89.1 1 1 El 1-1 RHR-208-D-12 VALVE TO ELBOW AUG 1 El I OWN PRE B-J HI 1El1-1 RHR-20B-D-13 A-23 IS1 89.1 1 1 El 1-1 RHR-208-D-13 ELBOWTO PIPE AUG 1 El 1 OWN PRE B-J H1 1 El 1-1 RHR-208-D-13A A-23 IS1 89.1 1 1 El 1-1 RHR-208-D-13A PIPE TO FLUED HEAD AUG 1 El 1 OWN PRE B-J HI 1 El 1-1 RHR-20B-D-14 89.1 1 1 El 1-1 RHR-208-0-14 1 El 1 A-23 FLUED HEAD TO PlPE IS1 AUG OWN PRE Page 20 - 35 1/12/2006 1 Period 1 Period 2 Period 3

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 22 - 35 111 212006 1 Period 1 Period 2 Period 3 (D h 2 2 I I - - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - . - . - . - - - - - - - - - - - - - - - - - - . - - Category, Iso No. ItemNO, Comp. Desc.

Scope I Method I Procedure Code Case Class Summary I ComplD 1 System B-J HI 1 El 1-1 RHR-24A-R-5 A-2 1 IS1 89.1 1 1 El 1 -lRHR-24A-R-5 PIPE TO ELBOW AUG 1 El 1 OWN PRE B-J HI 1 El 1-1 RHR-24A-R-6 A-21 IS1 89.1 1 1 El 1-1 RHR-24A-R-6 ELBOW TO ELBOW AUG 1 El 1 OWN PRE B J HI 1 El 1-1 RHR-24A-R-7 ISIII A-2 1 IS1 89.1 1 1 Ell-1 RHR-24A-R-7 ELBOW TO ELBOW AUG 1 El 1 OWN PRE B-J HI 1 El 1-1 RHR-24A-R-8 A-21 IS1 89.1 I 1 El 1 -lRHR-24A-R-8 ELBOW TO VALVE AUG 1 El I OM PRE B-J HI 1 El 1-1 RHR-24A-R-9 ISIII A-2 1 IS1 89.1 1 1 El 1-1 RHR-24A-R-9 ISlll VALVE TO PIPE AUG 1 El 1 ow PRE B J HI 1 El 1-1 RHR-24B-R-1 OA A-22 IS1 89.1 1 1 El 1-1 RHR-24B-R-1 OA VALVE TO REDUCER AUG 1 El 1 OWN PRE B-J HI 1 Ell-1 RHR-24B-R-10B IS111 A-22 IS1 89.1 1 1 El 1-1 RHR-24B-R-I OB REDUCER TO PIPE AUG 1 El 1 OWN PRE B-J HI 1 El 1-1 RHR-24B-R-11 A-22 IS1 89.1 1 1 El 1-1 RHR-24B-R-I 1 ELBOW TO VALVE AUG 1 El 1 om PRE B-J HI 1 El 1-1 RHR-24B-R-3 A-22 IS1 89.1 1 1 El 1-1RHR-24B-R-3 VALVE TO PIPE AUG 1 El 1 OWN PRE B-J HI 1 El 1-1 RHR-246-R-3A A-22 IS1 89.1 1 1 El 1-1 RHR-24B-R-3A PIPE TO FLUED HEAD AUG 1 El 1 om PRE N m P) I I 2 2 - - - - - . . - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - . - - - - - - - . - - - . - - - - - - - - - - - - . - - - . - - - - - - x I F .- ------------ - - - - - - - . - - - - ------------ - - - - - - . - - - - - -----s------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -s---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------s--- - - - - - - - - - - - . ------------ - - - - - - - - - - - - ------------ - . - - - - - - - - . . -.---------- - - - - - - - - - - . .

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1 HNP-1 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 HI 1 El 1-1 RHR-240-R-4 ISlll A-22 IS1 89.1 1 1 El 1-1 RHR-240-R-4 PIPE TO ELBOW AUG 1 El 1 OWN PRE B-J HI 1 El 1-1 RHR-240-R-5 A-22 IS\ 09.1 1 1 El 1-1 RHR-240-R-5 ELBOW TO ELBOW AUG 1 El 1 OWN PRE B-J H1 1 El 1-1 RHR-240-R-6 A-22 IS1 89.1 1 1 El 1-1 RHR-240-R-6 ELBOW TO PIPE AUG 1 El 1 OWN PRE B-J H1 1E11-1 RHR-24B-R-7 A-22 IS1 09.1 1 1 El 1 -1RHR-240-R-7 PIPE TO ELBOW AUG 1 El 1 OWN PRE B J H1 1E11-1 RHR-24B-R-8 A-22 IS1 09.1 1 1 El 1-1 RHR-24B-R-8 ELBOW TO PIPE AUG 1 El 1 OWN PRE B-J H1 1El1-1 RHR-240-R-9A A-22 IS1 09.1 1 1 El 1-1 RHR-248-R-9A PIPE TO REDUCER AUG 1 El 1 OWN PRE B-J H1 1 El 1-1 RHR-240-R-98 A-22 IS1 09.1 1 1 El 1-1 RHR-240-R-90 REDUCER TO VALVE AUG 1 El I OWN PRE B-J HI 1El1-1 RHR-9A-HS-1 A-25 IS1 09.1 1 1 El 1-1 RHR-9A-HS-1 5 314" DIA. FLANGE TO NOZZLE N6A AUG 1 El I OWN PRE B-J HI 1 El 1-1 RHR-9B-HS-1 A-25 IS1 89.1 1 1 El 1-1 RHR-98-HS-1 5 314" DIA. FLANGE TO NOZZLE N6B AUG 1 El I OWN PRE B J HI 1 E21-1 CS-1OA-1OA A-26 IS1 89.1 1 1 E21-1 CS-1 OA-1OA VALVE TO PIPE AUG 1 E2 1 OWN PRE Page 23 - 35 Period 1 Period 2 1/1212006 1 Period 3 2 z r 2 2 rn-5 q- I rn 2 0 2 cn l, 2 0 0 cn ? l. 00 t L!? '0 h) rn a -I 0 7 r C rn 0 I rn b 0 rnzo -gr 2 2 rn-5 rn 2 0 2 cn l, 0 0 cn ? l, !2 9 - v, : F z d n '0 rn n4c-n4cgn rnzo -gf 2 2 rn- yEE 2 - rn 2 0 cn l, L. 0 0 cn ? A N 0 ? N - E? c' d z I X 2 N 2 0 N 2 z 5 a d P w 2 rnso 2 s 2 2 2;Z 2 - I rn 2 0 2 cn l, 0 0 cn ? l, - 0 2 < 4 9 F z a 4 -I 0 n v rn mzo 2 r 2 2 scz 2 - ! rn 2 0 2 cn l 0 0 cn ? l, - 0 a 9

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

Class Summary / ComplD / System Scope / Method / Procedure Code Case B-J HI 1E21-1 CS-10A-3A A-26 IS1 89.1 1 1 E21-1 CS-10A-3A FLUED HEAD TO PIPE AUG 1 E21 OWN PRE B-J HI 1 E21-1 CS-10A-4 A-26 IS1 89.1 1 1 *21 -1 CS-10A-4 PIPE TO ELBOW AU G 1 E2 1 OWN PRE B-J HI 1 E21-1 CS-10A-5 A-26 IS1 89.1 1 1 E21-1 CS-10A-5 ELBOW TO PIPE AUG 1 E21 OWN PRE B-J HI 1 E21-1 CS-10A-6 A-26 IS1 89.1 1 1 E21-1 CS-10A-6 PIPE TO VALVE AUG 1 EZ1 OWN PRE B J HI 1 E21-1 CS-10A-7 A-26 IS1 89.1 1 1E21-1 CS-10A-7 VALVE TO ELBOW AUG 1 E21 OWN PRE B J HI 1 E21-1 CS-10A-8 A-26 IS1 89.1 1 1 E21-1 CS-10A-8 ELBOW TO PIPE AUG 1 E2 1 OWN PRE B-J HI 1 E21-1 CS-10A-9 ISIII A-26 IS1 89.1 1 1E21-1 CS-10A-9 ISlll PIPE TO VALVE AUG 1 E21 OWN PRE B-J HI 1 E21-1 CS-108-10 A-27 IS1 89.1 1 1 E21-1 CS-108-10 PIPE TO VALVE AUG 1 E2 1 OWN PRE B-J HI 1 E21-1 CS-108-11 A A-27 IS1 89.1 1 1E21-1 CS-108-11A VALVE TO PIPE AUG 1 E21 OWN PRE 6-J HI 1 E21-1 CS-108-1 2A A-27 IS\ PlPE TO ELBOW AUG OWN PRE Page 25 - 35 Period 1 Period 2 Period 3 Revision:

1 HNP-I Fourth Interval Class 1 IS1 Plan Page 26 - 35 Southern Nuclear Operating Company Period 1 Period 2 111212006 1 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-J H1 1 E21-1 CS-1OB-13A A-27 IS1 89.1 1 1 E21-1 CS-10B-13A ELBOW TO PIPE AUG 1 E21 om PRE B J HI IE21-1 CS-100-14A A-27 IS1 89.11 1 E21-1 CS-1 OB-14A PIPE TO ELBOW AUG 1 *2 1 OWN PRE B-J HI 1 E21-1 CS-100-15A A-27 IS1 89.1 1 1 E21-1 CS-1 0B-15A ELBOW TO PIPE AUG 1 E2 1 om PRE B-J ti1 1 E21-1 CS-IOB-16A A-27 IS1 89.1 1 1 E21-1 CS-10B-16A PIPE TO ELBOW AUG 1 E21 om PRE B-J HI 1 E21-1 CS-1 OB-17A A-27 IS1 89.1 1 1 E21-1 CS-100-17A ELBOW TO ELBOW AUG 1 E2 1 om PRE B J HI 1 E21-1 CS-1OB-18A A-27 IS1 09.1 1 1 E21-1 CS-10B-18A ELBOW TO PIPE AUG 1 E2 1 OWN PRE B J HI 1 E21-1 CS-1OB-2 A-27 IS1 89.1 1 1 E21-1 CS-I OB-2 VALVE TO ELBOW AUG 1 E21 OWN PRE B J HI 1 E21-1 CS-100-3 A-27 IS1 89.1 1 1 E21-1 CS-10B-3 ELBOW TO PIPE AUG 1 E21 om PRE B-J HI 1 E21-1 CS-100-4 A-27 IS1 89.1 1 1 E21 -lCS-10B-4 PIPE TO FLUED HEAD AUG 1 E2 1 OWN PRE B-J H1 1 E21-1 CS-10B-4A A-27 IS1 89.1 1 1 E21-1 CS-100-4A FLUED HEAD TO PIPE AUG 1 E21 ol,'l/N PRE d V) 2 2 I I 7 - - - - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - --.-s------- - - - - - - . - - - - - ------------ - - - . - - - - - - - - N m o 2 2 5 5 - - - - - - - - - - - . - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - . - - . - - - - - - - - - - . - Period 3 (D b 2 2 I I -S--- - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - s--- - - - - - - - - - . - - - - - - - - . - - - - - - - . - - . - - - - - -

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1 HNP-I 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 1 Procedure Code Case B J HI 1 E21-1 CS-108-5 A-27 IS1 89.1 1 1 E21-1 CS-10B-5 PIPE TO ELBOW AUG 1 E2 1 OWN PRE B-J HI 1 E21-1 CS-108-6 A-27 IS1 89.1 1 1 E21-1 CS-108-6 ELBOW TO PIPE AUG 1 E21 OWN PRF . . ,- B-J HI I E21-I CS-10B-7 A-27 IS1 89.1 1 1 E21-1 CS-108-7 PIPE TO VALVE AUG 1 E21 OWN PRE B-J H1 1 E21-1 CS-108-8 A-27 IS1 89.1 1 1 E21-1 CS-108-8 VALVE TO ELBOW AUG 1 E21 OWN PRE B J H1 1 E21-1 CS-108-9 A-27 IS1 89.1 1 1 E21-1 CS-108-9 ELBOW TO PIPE AUG 1 E21 OWN PRF . .- B-J HI 1 E21-2CS-10A-4 ISlll A-26 IS I 89.1 1 1 E21-2CS-10A-4 VALVE TO PIPE AUG 1 E21 OWN PRE B-J H1 1 E21-2CS-10A-5 A-26 IS1 89.1 1 1 E21-2CS-10A-5 PIPE TO VALVE AUG 1 E21 OWN PRE . .- B-J Hl 1 E21-2CS-108-5 A-27 IS1 89.1 1 1 E21-2CS-108-5 VALVE TO PIPE AUG 1 E21 OWN PRE B-J HI 1 E21-2CS-108-6 A-27 IS1 89.1 1 1 E21-2CS-108-6 PIPE TO VALVE AUG OWN PRE . .- B-J HI 1 E41-1 HPCI-10-D-1 IS Ill A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-I BRANCH CONNECTION TO PIPE AUG 1 E41 OWN PRE Page 27 - 35 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company Page 28 - 35 1/12/2006 ( Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Cornp. Desc. Class Summary I CornplD I System Scope I Method I Procedure Code Case B J H1 1 E41-1 HPCI-10-D-10 A-28 IS1 89.1 1 1 E41-1 HPCI-I O-D-10 PIPE TO ELBOW AUG 1 E4 1 OWN PRE B-J HI 1 E41-1 HPCI-10-D-11 A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-1 I ELBOW TO PIPE AUG 1 E4 1 OWN PRE B-J HI 1 E41-1 HPCI-10-D-12 A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-12 PIPE TO TEE AUG 1 E41 OWN PRE B J HI 1 E41-1 HPCI-10-D-13 A-28 IS1 89.11 1 E41-1 HPCI-1 O-D-I 3 TEE TO CAP AUG 1 E41 OWN PRE B-J HI 1 E41-1 HPCI-10-D-14 A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-14 TEE TO VALVE AUG 1 E41 OWN PRE B-J HI 1 E41-1 HPCI-10-D-15 A-28 IS1 89.1 1 1 E41-IHPCI-10-D-15 VALVE TO PIPE AUG 1 E41 OWN PRE B-J HI 1 E41-1 HPCI-lO-D-15 A-28 IS1 89.11 1 E41-1 HPCI-1 O-D-15A PIPE TO FLUED HEAD AUG 1 E41 OWN PRE B-J H1 1E41-1 HPCI-10-D-16 A-28 IS1 89.1 1 1 E41-1 HPCI-1 O-D-16 FLUED HEAD TO PIPE AUG 1 E41 OWN PRE B-J H1 1 E41-1 HPCI-10-D-17 A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-17 PIPE TO VALVE AUG 1 E41 OWN PRE B-J H1 1 E41-1 HPCI-10-0-2 A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-2 PIPE TO ELBOW AUG 1 E41 OWN PRE Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 29 - 35 Period 1 Period 2 111212006 1 Period 3 W h 2 2 x x r r - S-- - - - - . - . - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - . . - - - - - . - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Code Case Class Summary / ComplD / System Scope I Method I Procedure B-J HI 1 E41-1 HPCI-10-D-3 ISIIUTI A-28 IS1 89 11 1 E41-1 HPCI-10-D-3 ELBOW TO PIPE AUG 1 E41 OWN PRE B J H1 1 E41-1 HPCI-10-D-4 A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-4 PIPE TO ELBOW AUG 1 E41 OWN PRE B J HI 1 E41-1 HPCI-10-D-5 A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-5 ELBOW TO ELBOW AUG 1 E41 OWN PRE B-J HI 1 E41-1 HPCI-10-D-6 A-28 IS1 69 11 1 E41-1 HPCI-10-D-6 ELBOW TO PIPE AUG 1 E41 OWN PRE B J HI 1 E41-1 HPCI-10-D-6A A-28 IS1 69.1 1 1 E41-1 HPCI-I 0-D-6A PIPE TO ELBOW AUG 1 E41 OWN PRE B J H1 1 E41-1 HPCI-10-D-66 A-28 IS1 89.1 1 1 E41-1 HPCI-1 0-D-6B ELBOW TO PIPE AUG 1 E41 OWN PRE B-J HI 1 E4'-1 HPCI-10-D-6C ISIII A-28 IS1 89.1 1 1 E41-1 HPCI-10-D-6C ISIII PIPE TO ELBOW AUG 1 E41 OWN PRE 6 J HI 1 E41-1 HPCI-10-0-7 A-28 IS1 89.1 1 1 E41-1 HPCI-10-0-7 ELBOW TO PIPE AUG 1 E41 OWN PRE B-J HI 1 E41-1 HPCI-10-D-8 ISIl1 A-28 IS1 89.11 1 E41-1 HPCI-10-D-8 ISIII PIPE TO ELBOW AUG 1 E41 OWN PRE B J HI 1 E41-1 HPCI-10-D-9 A-28 IS1 89.1 1 1 E41-1 HPCI-I 0-D-9 ELBOW TO PIPE AUG 1 E41 OWN PRE m Ni.3 2 2 5 5 - - - - - - - - . - - - . - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - . - - - - - - - - - - - - d Y) 12 &? r I - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - . . - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -s---.------ - - . - - - - - - - - - ------------ - - - - - - - - - - - - --------s--- - - - - - - - . - - . . ------------ - . . - - . - - - . - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 30 - 35 Period 1 Period 2 1112'2006 1 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B J H1 1 E41-1 HPCI-14-R-10 A-29 IS1 89.1 1 1 E41-1 HPCI-14-R-10 PIPE TO ELBOW AUG 1 E41 OWN PRE B J HI 1 E41-1 HPCI-14-R-11 A-29 IS1 89.1 1 1 E41-1HPCI-14-R-11 ELBOW TO PIPE AUG 1 E41 OWN PRE B J HI 1 E41-1 HPCI-14-R-11 BC A-29 IS1 09.32 1 E41-1 HPCI-14-R-I 1 BC PIPE TO BRANCH CONNECTION AUG 1 E41 ow PRE BJ Hl 1E41-1 HPCI-14-R-12 A-29 IS1 89.1 1 1 E41-1 HPCI-14R-12 PIPE TO BRANCH CONNECTION AUG 1 E41 ow PRE B J HI 1 E41-1 HPCI-14-R-2 A-29 IS1 89.1 1 1 E41-1 HPCI-14-R-2 VALVE TO PIPE AUG 1 E41 OWN PRE B J H1 1 E41-1 HPCI-14-R-3 A-29 IS1 09 11 1 E41-1 HPCI-14-R-3 PIPE TO ELBOW AUG 1 E41 OWN PRE B J HI 1 E41-1 HPCI-14-R-4 A-29 IS1 89.1 1 1 E41-1 HPCI-14-R-4 ELBOW TO PIPE AUG 1 E41 ow PRE B J HI 1 E41-1 HPCI-14-R-5 A-29 IS1 89.1 1 I E41-1 HPCI-14-R-5 PIPE TO ELBOW AUG 1 E41 OWN PRE B-J HI 1 E41-1 HPCI-14-R-6 A-29 IS1 89.1 1 1 E41-1 HPCI-14-R-6 ELBOW TO PIPE AUG 1 E41 ow PRE BJ HI 1 E41-1 HPCI-14-R-7 A-29 IS1 89.1 1 1 E41-1 HPCI-14-R-7 PIPE TO PIPE AUG 1 E41 ow PRE m N o 2 2 z 5 . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - r 7 x x ------------ - - - - - - - - - - - - --------s--- - - - - - - - - - - - - --------s--- - - - - - - - - - - - - ------------ - - - - - - - - - - - - -------.---- - - - - - - - - - - - - ------------ - - - - - - . - - - - - -.---------- - - - - --------- - - - - ------------ - - - - - - - - - - - - ----------.- . - - - - - - . - - - - ----..--..-- - - - . - . . - - . - - (D r. r .- 2 2 x x - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - . . - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - - . - - - - . . - - - - . - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 31 - 35 111212006 ( Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Scope / Method / Procedure Code Case Class Summary 1 ComplD I System B J HI 1 E41-1 HPCI-14-R-8 ISI/UT/ A-29 IS1 89.1 1 1 E41-1 HPCI-14R-8 PIPE TO ELBOW AUG 1 E41 OWN PRE B-J HI 1 E41-1 HPCI-14-R-9 A-29 IS1 89.1 1 1 E41-1 HPCI-14-R-9 ELBOWTO PIPE AUG 1 E41 OWN PRE B-J HI 1 E41-1 HPCI-3-R-I A A-29A IS1 89.21 1 E41-1 HPCI-3-R-1 A FLANGE TO PIPE AUG 1 E41 OWN PRE B-J HI 1E41-1 HPCI-3-R-4 lSl// A-29A IS1 B9.21 1 E41-1 HPCI-3-R-4 FLANGE TO ELBOW AUG 1 E41 PRE B-J HI 1 E41-1 HPCI-3-R-5 A-29A IS1 89.21 1 E41-1 HPCI-3-R-5 ELBOW TO BRANCH CONNECTION AUG 1 E41 OWN pRE B-J HI 1 E51-1 RCIC-3-D-1 A-30 IS1 89.21 1 E51-1 RCIC-3-D-1 BRANCH CONNECTION TO ELBOW AUG 1 E51 OWN PRE B-J HI 1 E51-1 RCIC-3-D-2 A-30 IS1 89.21 1 E51-1 RCIC-3-D-2 ELBOW TO REDUCER AUG 1 E51 OWN PRE B-J HI 1E51-1 RCIC-4-D-10 ISIIUTI A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-10 PIPE TO ELBOW AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-D-11 A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-11 ELBOW TO PIPE AUG 1 E51 OWN PRE B-J HI 1 E51-1 RCIC-4-0-12 A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-12 PIPE TO ELBOW AUG 1 E5 1 om PRE d V) 2 8 5 5 - - - - - - - - - - - - - - . - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----S------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ---------S-- - - - - - - - - - - - - ------------ - - - - - - - - - - - - -.---------- - - - - - - - - - - . - N m (3 2 2 x r - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - . - - - - . - - - wt. 8 2 5 5 - S-- - - - - - . - - - - - - - - - - . - . - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - . - - - - . - - - - - - - . - - . . -

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

Class Summary I CornplD I System Scope I Method I Procedure Code Case B-J Hl 1E51-1 RCIC-4-D-13 A-30 IS1 89.11 1 E51-1 RCIC-4-D-13 ELBOW TO ELBOW AUG 1 E5 1 OWN PRE B-J H1 1 E51-1 RCIC-4-D-14 A-30 IS1 89.1 1 1 E51-1RCIC-4-D-14 ELBOW TO PIPE AUG 1 E5 1 OWN PRE B-J Hl 1 E51-1 RCIC-4-D-15 A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-15 PIPE TO ELBOW AUG 1 E5 1 OWN PRE B J HI 1 E51-1 RCIC-4-D-16 ISIIUTI A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-16 ELBOW TO TEE AUG 1 E51 OWN PRE 6 J HI 1 E51-1 RCIC-4-D-17 A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-17 TEE TO CAP AUG 1 E5 1 OWN PRE B J H1 1 E51-1 RClC-4-D-I 8 A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-18 TEE TO VALVE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-D-19 ISIIUTI A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-19 VALVE TO PIPE AU G 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-D-20 A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-20 PIPE TO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-D-20A A-30 IS1 89.1 1 1 E51-I RCIC-4-D-20A PIPE TO FLUED HEAD AUG 1 E5 1 OWN PRF . . .- B-J H1 1 E51-1 RCIC-4-D-21 A-30 IS1 891 1 1 E51-1 RCIC-4-D-21 FLUED HEAD TO ELBOW AUG 1 E51 OWN PRE Page 32 - 35 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I CornplD I System Scope I Method / Procedure Code Case B 4 HI 1 E51-1 RCIC-4D-22 ISI/UT/ A-30 IS1 89.11 1 E51-1 RCIC-4-D-22 ELBOW TO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-D-23 A-30 IS1 89.11 1 E51-1 RCIC-4-D-23 PIPE TO VALVE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-D-3 A-30 IS\ 89.11 1 E51-1 RCIC-4-D-3 REDUCER TO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4D-4 A-30 IS1 89.11 1 E51-1 RCIC-4-0-4 PIPE TO ELBOW AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4D-5 A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-5 ELBOW TO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-D-6 A-30 IS1 89.11 1 E51-1 RCIC-4-D-6 PIPE TO ELBOW AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4D-7 A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-7 ELBOWTO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-0-8 IS Ill A-30 IS1 89.1 1 1 E51-1 RCIC-4-0-8 1S11/ PIPE TO ELBOW AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4D-9 ISI/UTl A-30 IS1 89.1 1 1 E51-1 RCIC-4-D-9 ELBOW TO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-R-10 A-3 1 IS1 89.1 1 1 E51-1 RCIC-4-R-10 PIPE TO PIPE AUG 1 E51 OWN PRE Page 33 - 35 Period 1 Period 2 Period 3 Revision:

1 HNP-1 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-J HI 1 E51-1 RCIC-4-R-11 A-3 1 IS1 89.1 1 1 E51-1 RCIC-4-R-11 PIPE TO REDUCER AUG 1 E5 1 OWN PRE B-J HI 1E51-1 RCIC-4-R-2 A-31 IS1 89.1 1 1 E51-1 RCIC-4-R-2 VALVE TO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-R-3 A-3 1 IS1 89.1 1 1 E51-1 RCIC-4-R-3 PIPE TO ELBOW AU G 1 E51 OWN PRE B-J HI 1 E51-1 RCIC-4-R-4 A-31 IS1 89.1 1 1 E51-1 RCIC-4-R-4 ELBOW TO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-R-5 A-31 IS1 89.1 1 1 E51-1 RCIC-4-R-5 PIPE TO ELBOW AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-4-R-6 A-3 1 IS1 89.1 1 1 E51-1 RCIC-4-R-6 ELBOW TO PIPE AUG 1 E5 1 OWN PRE B-J H1 1 E51-1 RCIC-4-R-7 lSlll A-3 1 IS1 89.1 1 1 E51-1 RCIC-4-R-7 ISIII PIPE TO ELBOW AUG 1 E5 1 OWN PRE B J HI 1 E51-1 RCIC-4-R-8 A-31 IS1 89.1 1 1 E51-1 RCIC-4-R-8 ELBOW TO TEE AUG 1 E5 1 OWN PRE B-J HI 1E51-1 RCIC-4-R-9 A-3 1 IS1 89.1 1 1 E51-1 RCIC-4-R-9 TEE TO PIPE AUG 1 E5 1 OWN PRE B-J HI 1 E51-1 RCIC-6-R-1 A-3 1 IS1 89.1 1 1 ESI -1 RCIC-6-R-I REDUCER TO PIPE AUG 1 E5 1 OWN PRE Page 34 - 35 Period 1 Period 2 1112'2006 I Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Page 35 - 35 Southern Nuclear Operating Company Period 1 Period 2 111212006 1 Period 3 Category, Iso No. NP-J a 5 (D h ItemNO, Comp. Desc. Code Case 2 2 I x 2 2 Class Summary I ComplD 1 System Scope I Method I Procedure

$ 5 I 7 I r B-J HI 1E51-1 RCIC-6-R-2 A-31 IS1 ------------

89.1 1 1 E51-1 RCIC-6-R-2 PIPE TO TEE AUG - - - . - - - - - - - - 1 E51 OWN - - . . - - - - - . - - PRE - - . - - - . - - - - J HI 1 G31-1 RWCU-3-R-37 A-33 IS1 ------------

89.32 1 G31-1 RWCU-3-R-37 VALVEF039FLANGETOEXPANDER AUG - - - - - - - - - - - - 1 G31 OWN - - - - - - - - - . - - PRE - - - - - - - - - - - - B J HI 1 G31-1 RWCU-4-R-38A ISIII A-33 IS1 -s----------

89.1 1 1 G31-1 RWCU-4-R-38A EXPANDER TO ELBOW AUG - - - - - - - - - - - - 1 G31 OWN - - - - - - - - - - - - PRE - - - - - - - - - - - - B J HI 1 G31-1 RWCU-4-R-40 A-33 IS1 ------------

89.1 1 1 G31-1 RWCU-4-R-40 ELBOW TO PIPE AUG - - - - - - - - - - - - 1 G31 om - - - - - - - - - - - - PRE - - - - - - - - - - - - B-J HI 1 G31-1 RWCU-4-R-41 A-33 IS1 ------------

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 - 12 111 212006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Cornp. Desc. 1" KK "("r KK 1%: K 0: Class Summary I ComplD 1 System Scope 1 Method 1 Procedure Code Case NB J HI I B11-1 INST-2A-2 A-42 IS1 NB9.21 1 B11-1 INST-2A-2 PIPE TO PIPE AUG 1 B11 OWN PRE NB J HI 1 B11-1 INST-2A-3 A-42 IS1 NB9.21 181 1-1 INST-2A-3 PIPE TO ELBOW AUG 1 B11 om PRE NB J HI 1B11-1 INST-2A-4 ISIII A-42 IS1 NB9.21 1 B11-1 INST-2A-4 ELBOW TO PIPE AUG 1 B11 om PRE NB J HI 1B11-1 INST-2A-5 ISIII A-42 IS1 NB9.21 1 B11-1 INST-2A-5 PIPE TO SOCKOLET AUG 1 Bl I OWN PRE NB-J H1 1B11-1 INST-2B-2 A-42 IS1 NB9.21 1 B11-I INST-2B-2 PIPE TO PIPE AUG 1 B11 om PRE NB J HI 1 B11-1 INST-2B-3 A-42 IS1 NB9.21 1 B11-1 INST-2B-3 PIPE TO ELBOW AUG 1 B11 OWN PRE NB J HI 1 B11-1 INST-2B-4 A-42 IS1 NB9.21 1 B11-1 INST-28-4 ELBOW TO PIPE AUG 1 B11 OWN pRE NB J HI 161 1-1 INST-2B-5 A-42 IS1 NB9.21 1 B11-1 INST-28-5 PIPE TO SOCKOLET AUG 1 B11 OWN pRE NB-J HI 1 C41-1 SBLC-2-2 ISIIPTINMP-ES-024-301 A-44 IS1 NB9.21 1 C41-1 SBLC-2-2 SAFE-END TO TEE AUG 1 C41 OWN PRE NB J H1 1 C41-1 SBLC-2-3 A-44 IS1 NB9.21 1 C41-1 SBLC-2-3 TEE TO SAFE-END AUG 1 C41 om PRE I I ---------.-- - - - - - . - - - - - - ------------ - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - -------- - - - - - - - - - - - - ------------ - - . - - - - - - - - - ------------ - - - - - - - - - - - - -------.---- - - - - - - - . - - - - ------------ - - - - - - - - - - - - s.------..-- - - - - - - . - - - - - ----.---...- . - - - - - - - . - - . 5 5 - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - 5 = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - . . . - - - - - - - - - - - - - -

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1 HNP-1 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 HI 1 B31-1 RC-2DR-11 A-40 IS1 NB9.40 1831 -1 RC-2DR-11 ELBOW TO PIPE AUG 1 83 1 OWN PRE NB-J HI 1831-1 RC-2DR-12 A-40 IS1 NB9.40 1831-1 RC-2DR-12 PIPE TO ELBOW AUG 1 831 OWN PRE NB J HI 1831-1 RC-2DR-13 A-40 IS1 NB9.40 1831 -1 RC-2DR-13 ELBOW TO PIPE AUG I 831 OWN PRE NB J HI 1 B31-1 RC-2DR-14 A-40 IS1 NB9.40 1831 -1 RC-2DR-14 PIPE TO TEE AUG 1 83 1 OWN PRE NB J H1 1 B31-1 RC-2DR-15 A-40 IS1 NB9.40 1 831 -1 RC-2DR-15 TEE TO PIPE AUG 1 83 1 OWN PRE NB J HI 1831-1 RC-2DR-16 A-40 IS1 NB9.40 1 B31-1RC-2DR-16 PIPE TO VALVE AUG 1 83 1 OWN PRE NB-J HI 1831 -1 RC-2DR-17 A-40 IS1 NB9.40 1831 -1 RC-2DR-17 VALVE TO PIPE AUG 1 831 OWN PRE NB-J H1 1831-1 RC-2DR-18 A-40 IS1 NB9.40 1831-1 RC-2DR-18 PIPE TO VALVE AUG 1 831 OWN PRE NB-J HI 1B31-1RC-2DR-19 A-40 IS1 NB9.40 1 B31-IRC-2DR-19 PIPE TO PIPE AUG 1 831 OWN PRE NB-J HI 1B31-1 RC-2DR-2 A-40 IS1 NB9.40 1831 -1 RC-2DR-2 PIPE TO TEE AUG 1 83 1 OWN PRE Page 4 - 12 111 212006 1 Period 1 Period 2 Period 3 (PI. 2 2 I I -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 5 - 12 111 212006 1 Period 1 Period 2 Period 3 Category, lso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method 1 Procedure Code Case NB J HI 1831-1 RC-2DR-20 lSlll A-41 IS1 NB9.40 1831 -1 RC-2DR-20 PIPE TO PIPE AUG 1 831 OWN PRE NB-J HI 1831-1 RC-2DR-21 lSlll A-41 IS1 NB9.40 1831 -1 RC-2DR-21 TEE TO FllTlNG AUG 1 831 om PRE NB-J HI 1 B31-1 RC-2DR-22 ISIIPTI A-41 IS1 NB9.40 1831 -1 RC-2DR-22 PIPE TO PIPE AUG 1 831 om PRE NB-J HI 1831-1 RC-2DR-23 ISIIPTI A-41 IS1 NB9.40 1831 -1RC-2DR-23 PIPE TO ELBOW AUG 1 831 OWN PRE NB-J HI 1831-1 RC-2DR-24 ISllPTl A-41 IS1 NB9.40 1 831 -1 RC-2DR-24 ELBOW TO PIPE AUG 1 831 OWN PRE NB J HI 1831-1 RC-2DR-25 lSlll A-41 IS1 NB9.40 1831 -1 RC-2DR-25 PIPE TO ELBOW AUG 1 83 1 OWN PRE NB J HI 1831-1 RC-2DR-26 A-41 IS1 NB9.40 1831 -1 RC-2DR-26 ELBOW TO PIPE AUG 1 83 1 OWN PRE NB J HI 1831-1 RC-2DR-27 A-41 IS1 NB9.40 1 831 -1 RC-2DR-27 PIPE TO ELBOW AUG 1 831 OWN PRE NB J HI 1831 -1 RC-2DR-28 ISIIPTI A-41 JSI NB9.40 1 831 -1 RC-2DR-28 ELBOW TO PIPE AUG 1 831 om PRE NB-J HI 1 B31-1 RC-2DR-29 ISllPTl A-41 IS1 NB9.40 1831 -1 RC-2DR-29 PIPE TO ELBOW AUG 1 831 OWN PRE d Y) 2 2 5 5 - - - - - - - - - - - - . - - - ---------s-- - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - .--------s-- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - . - - - - - - - . - -s--------.- - - - - - - - - - - - - -s---------- - - - - - - . - - . - - m NP) 2 2 x I Y- Y- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - . - - - - - - - - - W h 2 2 r x Y- - S-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - s-- - . - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - . - - - -

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1 HNP-1 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 / Procedure Code Case NB-J HI 1831 -1 RC-2DR-3 A-40 IS1 NB9.40 1831 -1 RC-2DR-3 PIPE TO PIPE AUG 1 83 1 OWN PRE NB-J HI 1831 -1 RC-2DR-30 ISIIPTI A-41 IS1 NB9.40 1 631 -1 RC-2DR-30 ELBOW TO BEND AUG 1 83 1 0 WN PRE NB J HI 1831-1 RC-2DR-31 A-41 IS1 NB9.40 1831 -1 RC-2DR-31 BEND TO VALVE AUG 1 83 1 OWN PRE -- NB J H1 1831-1 RC-2DR-32 A-41 IS1 NB9.40 1831 -1 RC-2DR-32 VALVE TO PIPE AUG 1 83 1 OWN PRE NB J HI 1831-1 RC-2DR-33 A-41 IS1 NB9.40 1 831 -1 RC-2DR-33 PIPE TO TEE AUG 1 83 1 OWN PRE NB-J HI 1831-1 RC-2DR-34 A-41 IS1 NB9.40 1831 -1 RC-2DR-34 VALVE TO PIPE AUG 1 83 1 OWN PRE NB-J Hl 1831-1 RC-2DR-35 A-41 IS1 NB9.40 1831-1RC-2DR-35 PIPE TO PIPE AUG 1 83 1 OWN PRE NB-J HI 1831-1 RC-2DR-36 A-41 IS1 NB9.40 1831 -1 RC-2DR-36 PIPE TO REDUCER AUG 1 83 1 OWN PRE NB-J H1 1831-1 RC-2DR-37 A-41 IS1 NB9.40 1 831 -1 RC-2DR-37 REDUCER TO PIPE AUG 1 83 1 OWN PRE NB-J HI 1831-1 RC-2DR-38 A-41 IS1 NB9.40 1 831-1 RC-2DR-38 PIPE TO REDUCER AUG 1 831 OWN PRE Page 6 - 12 111 212006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope I Method I Procedure Code Case NB J HI 1831 -1 RC-2DR-39 A-41 IS1 NB9 40 1 B31-1 RC-2DR-39 TEE TO PIPE AUG 1 83 1 OWN PRF . . .- NB-J H1 1831-1 RC-2DR-4 A-40 IS1 NB9.40 1 B31-1 RC-2DR-4 REDUCER TO PIPE AUG 1 831 OWN PRE NB J HI 1831-1 RC-2DR-40 A-41 IS1 NB9.40 1 B31-IRC-2DR-40 REDUCER TO ELBOW AUG 1 831 OWN PRE NB J HI 1831-1 RC-2DR-41 A-41 IS1 NB9.40 1831 -1 RC-2DR-41 ELBOW TO PIPE AUG 1 83 1 OWN PRE NB J H1 1831-1 RC-2DR-42 A-41 IS1 NB9.40 1831-lRC-2DR-42 PIPE TO ELBOW AUG 1 83 1 OWN PRE . . .- NB J HI 1831-1 RC-2DR-43 A-41 IS1 NB9.40 1831 -1 RC-2DR-43 ELBOW TO PIPE AUG 1 B3 1 OWN PRE NB J HI 1831-1 RC-2DR-44 A-41 IS1 NB9.40 1831 -1 RC-2DR-44 PIPE TO ELBOW AUG 1 83 1 OWN PRF . . .- NB-J H1 1831-1RC-2DR-45 A-41 IS1 NB9.40 1831 -1 RC-2DR-45 ELBOW TO PIPE AUG 1 83 1 OWN PRE NB J HI 1831-1 RC-2DR-46 ISIIPTI A-41 IS1 NB9.40 1 B31-IRC-2DR-46 PIPE TO ELBOW AUG 1 B3 1 OWN PRE NB J Hl 1831-1 RC-2DR-47 ISllPTl A-41 IS1 NB9.40 1 B31-1 RC-2DR-47 ELBOW TO PIPE AUG 1 83 1 OWN PRE Page 7 - 12 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 8 - 12 111 212006 1 Period 1 Period 2 Period 3 Category, Iso No. NP) m d V) 2 2 5 I, - - - - - - - - - - - - - - - - ----------.- - - - - - - - - - - - - -.---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - .----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ . - - - - - - - - - - - ------------ - - - - - - - - - . - . -----s------ - . - - - - . - - - - - -s.-----.-.- - - - - - . - - - . - . ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method I Procedure Code Case NB J HI 1831-1 RC-2DR-48 ISllPTl A-41 IS1 NB9.40 1831 -1 RC-2DR-48 PIPE TO VALVE AUG 1 83 1 om PRE NB J HI 1831 -1 RC-2DR-49 A-41 IS1 NB9.40 1831 -1 RC-2DR-49 VALVE TO PIPE AUG 1 83 1 om PRE NB-J HI 1831-1 RC-2DR-5 A-40 IS1 NB9.40 1831 -1 RC-2DR-5 PIPE TO PIPE AUG 1 83 1 OWN PRE NB-J HI 1831-1 RC-2DR-50 A-41 IS1 NB9.40 1831 -1 RC-2DR-50 PIPE TO TEE AUG 1 831 om PRE NB-J HI 1831-1 RC-2DR-6 A-40 IS1 NB9.40 1631-1RC-2DR-6 PIPE TO ELBOW AUG 1 831 OWN PRE NB-J HI 1831-1 RC-2DR-7 A-40 IS1 NB9.40 1031 -1 RC-2DR-7 ELBOW TO PIPE AUG 1 831 om PRE NB-J HI 1031-1 RC-2DR-8 A-40 IS1 NB9.40 1831 -1 RC-2DR-8 PIPE TO ELBOW AUG 1 831 OWN PRE NB-J HI 1831-1 RC-2DR-9 A-40 IS1 NB9.40 1831 -1 RC-2DR-9 ELBOW TO PIPE AUG 1 83 1 om PRE NB-J HI 1 C41-1 SBLC-1.5-1 ISllPTl A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-1 VALVE TO PIPE AUG 1 C41 OWN PRE NB-J HI 1 C41-1 SBLC-1.5-10 ISllPTl A-45 IS1 NB9.40 1 C41-1SBLC-1.5-10 PIPE TO ELBOW AUG 1 C4 1 OWN PRE (D r- 2 2 r I 7 r - S-- - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - . - . . - - . . - - 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - . - - - - - - - . - - - . - - - - - - . - - - - - - - - - . - . - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 9 - 12 111 212006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Code Case Class Summary 1 CornplD 1 System Scope 1 Method I Procedure NB J H1 1 C41-1 SBLC-1.5-11 ISIIPTI A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-11 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J HI 1 C41-1 SBLC-1.5-12 lSllPT1 A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-12 PIPE TO ELBOW AUG 1 C41 OWN PRE NB-J H1 1 C41-1 SBLC-1.5-13 A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-13 ELBOW TO PIPE AUG 1 C41 OWN PRE NB-J HI 1 C41-1 SBLC-1.5-14 A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-14 PIPE TO ELBOW AUG 1 C41 OWN PRE NB-J HI 1 C41-1 SBLC-1.5-15 A-45 IS1 NB9.40 1 C41-1SBLC-1.5-15 ELBOW TO PIPE AUG 1 C41 OWN PRE NB-J HI 1 C41-1 SBLC-1.5-16 A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-16 PIPE TO PIPE AUG 1 C41 OWN pRE NB J HI 1 C41-1 SBLC-1.5-17 A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-17 PIPE TO REDUCER AUG 1 C41 OWN pRE NB-J H1 1 C41-1 SBLC-1.5-18 A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-18 TEE TO PIPE AUG 1 C41 OWN PRE NB J HI 1 C41-1 SBLC-1.5-19 A-45 IS1 NB9.40 1 C41-1SBLC-15-19 PIPE TO VALVE AUG 1 C41 OWN PRE NB-J H1 1 C41-1 SBLC-1.5-2 ISIIPTI A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-2 PIPE TO ELBOW AUG 1 C41 OWN PRE

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1 HNP-1 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 HI 1 C41-1 SBLC-1.5-20 A-45 IS1 NB9.40 1 C41-1SBLC-1.5-20 VALE TO PIPE AUG 1 C41 OWN PRF . . .- NB J H1 1C41-1 SBLC-1.5-21 A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-21 PIPE TO FLOW ELEMENT AUG 1 C41 OWN PRE NB J HI 1 C41-1SBLC-1.5-22 A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-22 FLOW ELEMENT TO PIPE AUG 1 C41 OWN PRE . . .- NB J HI 1 C41-1 SBLC-1.5-23 A-45 IS1 NB9.40 1 C41-ISBLC-1.5-23 PIPE TO FLOW ELEMENT AUG 1 C41 OWN PRE NB-J H1 1 C41-1 SBLC-1.5-24 A-45 IS1 NB9.40 1 C41-1SBLC-1.5-24 FLOW ELEMENT TO PIPE AUG 1 C41 OWN PRE . . .- NB J HI 1 C41-1 SBLC-1.5-25 ISIIPTI A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-25 PIPE TO ELBOW AUG 1 C41 OWN PRE NB J HI 1 C41-1 SBLC-1.5-26 ISIIPTI A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-26 ELBOW TO PIPE AUG 1 C41 OWN PRE NB J HI 1 C41-1 SBLC-1.5-27 ISIIPTI A-45 IS1 NB9.40 1 C41-1 SBLC-1.5-27 PIPE TO PIPE AUG 1 C41 OWN PRE - NB J HI 1 C41-1 SBLC-1 5-28 A-45 IS1 NB9.40 1 C41-1SBLC-1.5-28 PIPE TO PIPE AUG 1 C41 OWN PRE NB J HI 1 C41-1 SBLC-1.5-29 A-45 IS1 NB9 40 1 C41-1 SBLC-1.5-29 TEE TO PIPE AUG 1 C41 OWN PRE Page 10- 12 Period 1 Period 2 Period 3

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 3 - 10 111 212006 1 Period 1 Period 2 Period 3 WI- 2 2 5 5 - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - . - - - - - - - . - . . - - - - - I r r T -.-----.---- - . - - - - - - - - - . -------..---- - . - - - - - - - - - - ------------ - - - - - - - - - - - - -----.------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -------.---- - - - - - . - - - - - - ------------ - - - - - - - - - - - - ----------.- - - - - - - . - - - - - ------..---- - - - - - - - - - - . . -------..--- - - - - - - - - - . - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B-K HI 1 B21-1 MS-24A-8HL-1 THRU 8 A-4 IS1 B10.20 1 B21-1MS-24A-8HL-1 THRU 8 B21 -SS2 AUG 1 821 OWN PRE B-K HI 1 B21-1 MS-24A-8PS-A-1 AND 2 A-4 IS1 B1 0.20 1821 -1 MS-24A-8PS-A-1 AND 2 B21 -HA2 AUG 1 821 om PRE B-K HI 1 B21-1 MS-24A-8PS-B-1 AND 2 A-4 IS1 81 0.20 1821-1MS-24A-8PS-B-1 AND 2 B21 -HA2 AUG 1 821 OWN PRE B -K HI 1821-1 MS-24A-8PS-C-1 AND 2 A-4 IS1 B1 0.20 1 B21-1 MS-24A-8PS-C-1 AND 2 821 -HA3 AUG 1 821 OWN PRE B -K HI 1 B21-1 MS-24A-8PS-D-1 AND 2 A-4 IS1 B1 0.20 1 B21-1 MS-24A-8PS-0-1 AND 2 B21 -HA3 AUG 1 821 om PRE B-K HI 1 B21-1 MS-24B-14SL-1 THRU 4 A-5A IS1 B1 0.20 1821 -lMS-24B-14SL-1 THRU 4 B21-GB1 AUG 1 821 OWN PRE B -K H1 1821-1MS-248-5HL-1 THRU 4 A-5 IS1 B10.20 1821 -lMS-24B-5HL-1 THRU 4 B21-HB1 AUG 1 B21 om PRE 6-K HI 1821-1MS-248-8HL-1 THRU 8 A-5 IS1 B10.20 1821 -lMS-24B-8HL-1 THRU 8 B21 -SS6 AUG 1 B21 OWN PRE B-K HI 1 B21-1 MS-240-8PS-A-1 AND 2 A-5 IS1 81 0.20 1821 -1 MS-24B-8PS-A-1 AND 2 B21 -HB2 AUG 1 B21 OWN PRE B-K HI 1821-1 MS-24B-8PS-B-1 AND 2 A-5 IS1 B1 0.20 1 B21 -lMS-24B-BPS-B-1 AND 2 B21-HB2 AUG 1 B21 OWN PRE rn m cs 2 2 5 ,I - . - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - . - . . - - - . -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 6 - 10 111 212006 1 Period 1 Period 2 Period 3 w I. 2 2 I I - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - .. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - . - - - - . - - - - - - . - Category, Iso No. ItemNO, Comp. Desc. Scope I Method 1 Procedure Code Case Class Summary I ComplD I System 6-K HI 1831-1 RC-22BM-3HL-A-1 AND 2 A-1 7 IS1 810.20 1 831 -1 RC-22BM-3HL-A-1 AND 2 B31-HB3 AUG 1 83 1 om PRE 6 -K HI 1831-1 RC-22BM-3HL-B-1 AND 2 A-1 7 IS1 81 0.20 1 831 -1 RC-22BM-3HL-B-1 AND 2 B31-HB3 AUG 1 831 OWN PRE B -K HI 1 B31-1 RC-28A-14HL-1 THRU 4 A-1 4B IS1 B10.20 1831-1 RC-28A-14HL-1 THRU 4 83 1 -HA2 AUG 1 83 1 OWN PRE 6-K HI 1831-1 RC-28A-15RL-1 AND 2 A-1 4B IS I 81 0.20 1 B31-1 RC-28A-15RL-1 AND 2 B31-SSA13 AUG 1 83 1 om pRE 6-K HI 1831-1 RC-28A-15RL-3 AND 4 A-1 48 IS1 810.20 1831 -1 RC-28A-15RL-3 AND 4 B31-SSA12 AUG 1 831 OWN PRE 6-K HI 1831-1 RC-28A-5HL-1 THRU 4 A-1 4 IS1 B10.20 1831 -1 RC-28A-5HL-1 THRU 4 B31 -HA1 AUG 1 831 OWN PRE 6-K HI 1831-1 RC-28B-15HL-1 THRU 4 A-15B IS1 81 0.20 1831 -1 RC-28B-15HL-1 THRU 4 B31-HB2 AUG 1 83 1 om pRE 6-K HI 1831-1 RC-28B-16RL-1 AND 2 A-1 5B IS1 81 020 1831-1 RC-28B-16RL-1 AND 2 B31-SSB13 AUG 1 83 1 OWN pRE 6-K HI 1831-1 RC-28B-16RL-3 AND 4 A-1 5B IS1 B10.20 1831 -1 RC-28B-16RL-3 AND 4 B31-SSB12 AUG 1 83 1 OWN PRE 6-K HI 1831-1 RC-28B-6HL-1 THRU 4 A-1 5 IS1 81 0.20 1831 -1 RC-28B-6HL-1 THRU 4 B31-HB1 AUG 1 831 OWN PRE CY 4 o 2 2 5 5 . - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - . - - . - - - - - . - - . - - - - . . - - - - . - - - - - - d 1.7 2 2 I r ------------ - - - - - - . - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - . - - - - - -s------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - - - - . - - - - ------------ - - - - - - - - - - - - ------------

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 7 - 10 111 212006 1 Period 1 Period 2 Period 3 (D h P 2 r F F I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - . - - - - - - - - - - - - - - - - . - - - . - - - - - - - - - - - I I ------------ - - - - - - - - - - - - ---------s-- - - - - - - - - - - - - ------------ - - - - - - - - - - - - -S---------- - - - - - - - - - - - - ------------ . - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - . - - - ------------ - - - - - - - - - - - - s - - - - - - - - . - - - . - - Category, Iso No. IternNO, Cornp. Desc. Scope I Method I Procedure Code Case Class Summary I CornplD I System B -K HI 1 El 1-1 RHR-20B-D-13PS A-23 IS1 810.20 1 El 1-1 RHR-20B-D-13PS El 1-RHRH-329 AUG 1 El 1 om PRE B -K HI 1 El 1-1 RHR-20B-D-13RL-1 THRU 4 lSlIMT1 A-23 IS1 B10.20 1 El 1-1 RHR-20B-D-13RL-1 THRU 4 El 1-RHRH-813 AUG 1 El 1 om pRE B-K HI 1Ell-1 RHR-20B-D-9HL-1 THRU 4 A-23 IS1 B1 0.20 1 El 1-1 RHR-20B-D-9HL-1 THRU 4 El 1-RHRH-328 AUG 1 El 1 OWN PRE B -K H1 1 El 1-1 RHR-24A-R-6RL-1 AND 2 A-2 1 IS1 810.20 1 El 1-lRHR-24A-R-6RL-1 AND 2 El 1-RHRH-137 AUG 1 El 1 OWN PRE B-K HI 1 El 1-1 RHR-24B-R-IOHL A-22 IS1 B1 0.20 1 El 1-1 RHR-24B-R-I OHL El 1-RHRH-143 AUG 1 El 1 om PRE B -K HI 1 El 1-1 RHR-24B-R-5RL-1 AND 2 A-22 IS1 81 0.20 1 El 1-1 RHR-24B-R-SRL-1 AND 2 El 1-RHRH-141 AUG 1 El 1 OWN PRE B-K HI 1 El 1-1 RHR-CHS-6RL-1 THRU 4 A-24 IS1 81 0.20 1 El 1-1 RHR-4-HS-6RL-1 THRU 4 El 1-RHRH-811 AUG 1 El 1 OWN PRE B-K HI 1 E21-1 CS-1OA-1OAHL-1 A-26 IS1 B10.20 1 E21-1CS-1OA-1OAHL-1 E21 -CSH-40 AUG 1 E21 OWN PRE B -K HI 1E21-1 CS-1OA-4PS A-26 IS1 B1 0.20 1 E21-1 CS-1 OA-4PS E21 -CSH-80 AUG 1 E2 1 om PRE B -K H1 1 E21-1 CS-1 OA-5PS A-26 IS1 B10.20 1 E21-1 CS-1 OA-5PS E21 -CSH-39 AUG 1 E2 1 om PRE (Y a el 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - . - - - - - - - - . - - - - - - - - - - - - - . ---- . - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 8 - 10 111 212006 I Period 1 Period 2 Period 3 w h 2 2 5 5 . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - . - - - - - - - . - - - - - - - - - - . I r ---.-------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ..------.---- - - - - - - - - - - - - -S---------- - - - - - - - . - - - - --------S--- - - - - - - - - - - - - -------.---- - - - - - - . - - . - - --------..-- - - - - - - . - - - - - .----------- - - - . - . - - - - - - Category, Iso No. IternNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case B -K HI 1 E21-1 CS-1OB-11AHL-1 A-27 IS1 B1 0.20 1 E21 -lCS-1 OB-I IAHL-I E21-CSH-34 AUG 1 E21 OWN PRE B-K HI 1 E21-1 CS-10B-4APL-5 THRU 8 A-27 IS1 B1 0.20 1 E21-1 CS-I OB-4APL-5 THRU 8 E21 -CSH-802 AUG 1 E21 OWN PRE B-K HI 1 E21-1 CS-1 OB-6PS-1 A-27 IS1 B1 0.20 1 E21-1 CS-1 OB-6PS-I E21-CSH-33 AUG 1 E2 1 om PRE B -K H1 1 E41-1 HPCI-10-D-11 HL-1 A-28 IS1 B10.20 1 E41-1 HPCI-1 0-D-1 1 HL-1 E41 -SS-20 AUG 1 E41 OWN PRE B -K H1 1 E41-1 HPCI-10-D-7HL-A-1 A-28 IS1 B10.20 1 E41-1 HPCI-10-D-7HL-A-1 E41 -SS-8 AUG 1 E41 om PRE B -K H1 1 E41-1 HPCI-10-D-7HL-B-1 AND 2 A-28 IS1 B1 0.20 1 E41-1 HPCI-10-D-7HL-B-1 AND 2 E41 -SS-22 AUG 1 E41 OWN PRE B -K H1 1 E41-1 HPCI-10-D-7SL-A-1 THRU 8 A-28 IS1 B10.20 1 E41-1 HPCI-10-D-7SL-A-1 THRU 8 E41 -HPSEH-52 AUG 1 E41 om PRE B -K H1 1 E41-1 HPCI-10-D-9HL-1 THRU 8 A-28 IS1 81 0.20 1 E41-1 HPCI-1 0-D-9HL-1 THRU 8 E41-SS-17 AUG 1 E41 OWN PRE B -K HI 1 E51-1RCIC-4-D-7HL-1 THRU 8 A-30 IS1 BlO 20 1 E51-1 RCIC-4-D-7HL-I THRU 8 E51 -SS-44 AUG 1 E5 1 OWN PRE B -K HI 1 E51-1 RCIC-4-D-7SL-1 THRU 6 A-30 IS1 B10.20 1 E51-1RCIC-4-D-7SL-I THRU 6 E51-RCSEH-19 AUG 1 E51 OWN PRE N m m 2 2 r r r l- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - . .

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1 HNP-1 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-K HI 1 E51-1 RCIC-CD-9SL A-30 IS1 81 0.20 1 E51-1 RCIC-4-D-9SL E51-RCSEH-18 AUG 1 E5 1 OWN PRE B -K HI 1 G31-1 RWCUM-6-D-12-HL-1 THRU 4 A-32 IS1 810.20 1 G31-1 RWCUM-6-D-12-HL-1 THRU 4 G31 -RWCUH-1 AUG 1 G31 OWN PRE B-K HI 1 G31-1 RWCUM-6-D-12-PS-1 THRU 8 A-32 IS1 81 0.20 1 G31-1 RWCUM-6-D-12-PS-1 THRU 8 1 G31-1 RWCUM-6-D-SM-7 AUG 1 G31 OWN PRE B -K HI 1 G31-1 RWCUM-6-D-18-RL-1 THRU 4 A-32 IS1 810.20 1 G31-1 RWCUM-6-D-18-RL-1 THRU 4 G31 -RWCUH-3 AUG 1 G31 OWN PRE B -K HI 1831\RC-A PUMP LUG-1 A-20 IS1 810.30 1 831\RC-A PUMP LUG-1 RESTRAINT LUG AUG 1 631 OWN PRE B-K HI 1 831\RC-A PUMP LUG-2 A-20 IS1 81 0.30 1631

\RC-A PUMP LUG-2 RESTRAINT LUG AUG 1 831 OWN PRE B -K HI 1631\RC-A PUMP LUG-3 A-20 IS1 81 0.30 1831 \RC-A PUMP LUG-3 RESTRAINT LUG AUG 1 831 OWN PRF . . .- B-K HI 1B31\RC-B PUMP LUG-I A-20 IS1 81 0.30 1631 \RC-8 PUMP LUG-1 RESTRAINT LUG AUG 1 631 OWN PRE B-K HI 1 831\RC-8 PUMP LUG-2 A-20 IS1 81 0 30 1831 \RC-8 PUMP LUG-2 RESTRAINT LUG AUG 1 831 OWN PRE B-K HI 1 831\RC-8 PUMP LUG-3 A-20 IS1 Bl 0 30 1631 \RC-8 PUMP LUG-3 RESTRAINT LUG AU G 1 831 OWN PRE Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class I IS1 Plan Southern Nuclear Operating Company Page10- 10 111212006 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 m N VJ 2 2 I I 7 7 s: K K I r 7 7 (P h 2 2 5 5 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 1 - I 111212006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD I System Scope I Method I Procedure Code Case B-L-2 HI 1831 \RC-A PUMP CASING lSll1 A-20 IS1 81 2.20 1 831 \RC-A PUMP CASING IDPUMPSURFACE IFDISASSEMBLED AUG 1 83 1 OWN PRE B-L-2 HI 1 B31\RC-8 PUMP CASING ISIII A-20 IS1 81 2.20 1831 \RC-B PUMP CASING IDPUMPSURFACE IFDISASSEMBLED AUG 1 83 1 OWN PRE m N C) 2 2 5 5 - - - - - - . - - - - . - - - - - - . - - - - - d U, 2 2 I I s----------- - - - - - - . - - - - - s----------- - - - - - - - - - - - - W h 2 2 I I 7 7 - - - - - . - - - - - - - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case B-M-2 HI 1 B21-F010A Body ISINTINMP-ES-024-201 A-8 IS1 B12.50G1 1821 -F010A Body GROUP 1 VALVE BODIES AUG 1 821 OWN PRE B-M-2 H1 1 B21-F01 0B Body ISllVTINMP-ES-024-201 A-9 IS1 B12.50Gl 1821 -F010B Body GROUP 1 VALVE BODIES AUG 1 821 OWN PRE B-M-2 H1 1821 -F032A Body ISllVTINMP-ES-024-201 A-8 IS1 B12.50Gl 1 B21-F032A Body GROUP 1 VALVE BODIES AUG 1 B21 OWN PRE B-M-2 H1 1 B21-F032B Body ISINTINMP-ES-024-201 A-9 IS1 B12.50Gl 1821 -F032B Body GROUP 1 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1 El 1-F060A Body ISINTINMP-ES-024-201 A-21 IS1 01 2.50G10 1 El 1 -F060A Body GROUP 10 VALVE BODIES AUG 1 El 1 OWN PRE B-M-2 H1 1 El 1 -F060B Body ISllVTINMP-ES-024201 A-22 IS1 B12.50G10 1 El 1-F060B Body GROUP 10 VALVE BODIES AUG 1 El 1 OWN PRE B -M -2 H1 1E21-F004A Body ISllWINMP-ES-024-201 A-26 IS1 B12.50G11 1 E21 -F004A Body GROUP 11 VALVE BODIES AUG 1 E21 OWN PRE B-Md HI 1 E21-F004B Body ISINTINMP-ES-024-201 A-27 IS1 B12.50G11 1 E21-F004B Body GROUP 11 VALVE BODIES AUG 1 E21 OWN PRE B-M-2 H1 1 E21-F005A Body ISINTINMP-ES-024-201 A-26 IS1 B12.50G11 1 E21 -F005A Body GROUP 11 VALVE BODIES AUG 1 E2 1 OWN PR E B-M-2 HI 1E21-F005B Body ISIIVTINMP-ES-024-201 A-27 IS1 B12.50Gll 1 E21 -F005B Body GROUP 11 VALVE BODIES AUG 1 E21 OWN PRE Period 1 Page I - 6 Period 2 Period 3 Revision:

1 HNP-1 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 I Procedure Code Case B-M-2 H1 1 E21 -F006A Body ISllVTINMP-ES-024201 A-26 IS1 B12.50G12 1 E21 -F006A Body GROUP 12 VALVE BODIES AUG 1 E21 OWN PRE B-M-2 HI 1 E21-F006B Body ISllVTINMP-ES-024201 A-27 IS1 B1 2.5061 2 1 E21 -F006B Body GROUP 12 VALVE BODIES AUG 1 E2 1 OWN PRE B-M-2 H1 1 E21 -F007A Body ISllVTINMP-ES-024201 A-26 IS1 B12.50G13 1 E21 -F007A Body GROUP 13 VALVE BODIES AUG 1 E2 1 OWN PRE B-M-2 HI 1 E21 -F007B Body ISIIVTINMP-ES-024201 A-27 IS1 B1 2.5001 3 1 E21 -F007B Body GROUP 13 VALVE BODIES AUG 1 E2 1 OWN PRE B-M-2 HI 1 E41 -F006 Body ISINTINMP-ES-024201 A-29 IS1 B12.50G14 1 E41 -F006 Body GROUP 14 VALVE BODIES AUG 1 E41 OWN PRE B-M-2 HI 1 E41 -F002 Body ISl/VTINMP-ES-024201 A-28 IS1 B12.50G15 1 E41-F002 Body GROUP 15 VALVE BODIES AUG 1 E41 OWN PRE B-M-2 HI 1 E41 -F003 Body ISllVTINMP-ES-024201 A-28 IS1 B12.50G15 1 E41 -F003 Body GROUP 15 VALVE BODIES AUG 1 E41 OWN PRE B-M-2 HI 1 G31-F001 Body ISINTINMP-ES-024201 A-32 IS1 B12.50G16 1 G31-F001 Body GROUP 16 VALVE BODIES AUG 1 G31 OWN PRE B-M-2 HI 1G31 -F004 Body ISllVTINMP-ES-024201 A-32 IS1 B12.50G16 1G31-F004 Body GROUP 16 VALVE BODIES AUG 1 G31 OWN PRE B-M-2 HI 1 G31 -F027 Body ISINTINMP-ES-024201 A-32 IS1 81 2.50G17 1 G31 -F027 Body GROUP 17 VALVE BODIES AUG 1 G31 OWN PRE Page 2 - 6 Period 2 Period 3 Revision:

1 HNP-1 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-M-2 H1 1821-F011A Body ISllVTINMP-ES-024201 A-8 IS1 81 2.50G2 1821 -F011A Body GROUP 2 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1621-FO11 B Body ISIIWINMP-ES-024-201 A-9 IS1 81 2.50G2 1621 -FOl 1 B Body GROUP 2 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1621-F013A Body ISINTINMP-ES-024-201 A-4 IS1 81 2.50G3 1821 -F013A Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1821-F013B Body ISIIVTINMP-ES-024-201 A-4 IS1 81 2.5063 1821 -F013B Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1821-F013C Body ISIIVTINMP-ES-024201 A-5 IS I 81 2.50G3 1821 -F013C Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1 B21-F013D Body ISIIVTINMP-ES-024201 A-5 IS1 81 2.50G3 1821 -F013D Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE B-M-2 H1 1821 -F013E Body ISllVTlNMP-ES-024201 A-5 IS1 81 2.50G3 1 821 -F013E Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1821-F013F Body ISIIVTINMP-ES-024201 A-6 IS1 81 2.50G3 1821 -F013F Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1821-F013G Body ISIIVTINMP-ES-024201 A-6 IS1 81 2.50G3 1 821 -F013G Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE -- B-M-2 H1 1821-F013H Body ISIIVTINMP-ES-024-201 A-7 IS1 81 2.50G3 1 821 -F013H Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE Page 3 - 6 21112006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-I Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 4 - 6 2/1/2006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Cornp. Desc.

Class Summary I CornplD I System Scope I Method I Procedure Code Case

-- B-M-2 HI 1821-F013J Body ISllVTINMP-ES-024-201 A-7 IS1 81 2.5063 1021 -F013J Body GROUP 3 VALVE BODIES AUG 1 82 1 OWN PRE B-M-2 HI 1821-F013K Body ISllVTlNMP-ES-024-201 A-5 IS1 81 2.5063 1 021 -F013K Body GROUP 3 VALVE BODIES AUG 1 82 1 OWN PRE B-M-2 HI 1021-F013L Body ISINTINMP-ES-024-201 A-6 IS1 81 2.5063 1021 -F013L Body GROUP 3 VALVE BODIES AUG 1 821 OWN PRE B-M-2 H1 1 821 -F022A Body ISllVTlNMP-ES-024-201 A-4A IS1 81 2.5064 1 021 -F022A Body GROUP 4 VALVE BODIES AUG 1 82 1 OWN PRE B-M-2 HI 1021-F022B Body ISINTINMP-ES-024-201 A-5A IS1 81 2.5064 1 821 -F022B Body GROUP 4 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1021-F022C Body ISINTINMP-ES-024201 A-6A IS1 81 2.5064 1 821 -F022C Body GROUP 4 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1821-F022D Body ISIIVTINMP-ES-024-201 A-7A ISI 81 2.50G4 1 821 -F022D Body GROUP 4 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1821 -F028A Body ISIIVTINMP-ES-024-201 A-4A IS1 81 2.5064 1 821 -F028A Body GROUP 4 VALVE BODIES AUG 1 821 OWN PRE B-M-2 H1 1 021 -F028B Body ISllVTINMP-ES-024-201 A-5A IS1 81 2.5064 1021 -F028B Body GROUP 4 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1021-F028C Body ISllVTlNMP-ES-024-201 A-6A IS1 81 2.5064 1 021 -F028C Body GROUP 4 VALVE BODIES AUG 1 821 OWN PRE Revision:

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

Class Summary 1 CornplD 1 System Scope 1 Method 1 Procedure Code Case B-M-2 HI 1621-F028D Body ISllVTINMP-ES-024201 A-7A IS1 81 2.50G4 1 821 -F028D Body GROUP 4 VALVE BODIES AUG 1 821 OWN PRE B-M-2 HI 1831-F023A Body ISINTINMP-ES-024201 A-I 4 IS1 81 2.50G5 1 831 -F023A Body GROUP 5 VALVE BODIES AU G 1 83 1 OWN PRE B-M-2 HI 1831-F023B Body ISINTINMP-ES-024-201 A-I 5 IS1 81 2.50G5 1 831 -F023B Body GROUP 5 VALVE BODIES AUG 1 831 OWN PRE B-M-2 HI 1831-F031A Body ISllVTINMP-ES-024201 A-I 48 IS1 81 2.50G5 1831-F031A Body GROUP 5 VALVE BODIES AUG 1 831 OWN PRE B-M-2 HI 1831 -F031B Body ISINTINMP-ES-024201 A-I 58 IS1 81 2.50G5 1831 -F031B Body GROUP 5 VALVE BODIES AU G 1 631 OWN PRE B-M-2 HI 1 El 1 -F008 Body ISIMINMP-ES-024201 A-23 IS1 81 2.50G6 1 El 1-F008 Body GROUP 6 VALVE BODIES AUG 1 Ell OWN PRE B-Md HI 1 El 1 -F009 Body ISIIVTINMP-ES-024201 A-23 IS1 81 2.50G6 1 El 1 -F009 Body GROUP 6 VALVE BODIES AUG 1 El I OWN PRE B-M-2 HI 1 El 1 -F015A Body ISIMINM P-ES-024201 A-21 IS1 81 2.50G7 1 El 1 -F015A Body GROUP 7 VALVE BODIES AUG 1 El I OWN PRE B-M-2 H1 1 El 1-F015B Body ISllVTINM P-ES-024201 A-22 IS1 81 2.50G7 1 El 1 -F015B Body GROUP 7 VALVE BODIES AUG 1 El I OWN PRE B-M-2 HI 1 El 1 -F067 Body ISllVTINMP-ES-024201 A-23 IS1 81 2.50G8 1 El 1 -F067 Body GROUP 8 VALVE BODIES AUG 1 El I OWN PRE Page 5 - 6 21112006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Page 6 - 6 211 12006 1 Period 1 Period 2 Period 3 GROUP 9 VALVE BODIES Wb 2 2 5 5 I, 5 s-----------

Category, Iso No. IternNO, Cornp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case B-M-2 HI 1 El 1 -F050A Body ISIIVTINMP-ES-024-201 A-21 IS1 PRE B-M-2 HI 1 El 1 -F050B Body ISIIVTINMP-ES-024-201 A-22 IS1 81 2.50G9 1 El 1 -F050B Body GROUP 9 VALVE BODIES AUG 1 El 1 om 4 0 2 2 I, 5 - - - - - - - - - - - - - - - - s----------- - - - - - - - - - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Class 1 IS1 Plan Southern Nuclear Operating Company Period 1 Category, IternNO, lso No. Cornp. Desc. Class Summary I CornplD I System Scope I Method I Procedure Code Case 814.10 IBlI\RPVWELDS 1 Bll CRD HOUSING (Inaccessible)

AUG OWN PRE Page 1 - 1 Period 2 Period 3 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 1 of 33 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 Class 2 components is made by Design Modifications and designated on the ISI Boundary Diagrams.

These Boundary Diagrams are controlled by Design

Modifications.

System Boundaries The system boundaries for Code Class 2 are designated on the ISI Boundary Diagrams.

EXAMINATION REQUIREMENTS The examination requirements for the Cla ss 2 components identif ied on the Boundary Diagrams are defined in IWC-2500 for each examination 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

The following Categories are not applicable to HNP.

Category C-D Pressure Retaining Bolting Greater than 2" Diameter (NA to HNP) Category C-F-1 Pressure Retaining Welds in Austenitic Stainless St eel or High Alloy Steel Piping (NA to HNP) Category C-G Pressure Retaining Welds in Pumps and Valves (NA to HNP)

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

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc 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 to be used during the 4 th Interval are the same as those used during the 3 rd Interval and include:

1. Size Exemption - All components less 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 a ny size 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 evalua ted and discussed below for application at HNP-1.

1. Size Exemption - For a BWR, the size exemption applies 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-1 is described below.

Residual Heat Removal (RHR) Function - Per Section 4.8.3 of the UFSAR, the objective of the RHR system is to restore and maintain the coolant inventory in the reactor vessel so that the core is adequately cooled af ter a loss-of-coolant accident (LOCA). The RHR system also provides containment cooling so that condensation of the steam resulting from the blowdown due to the design basis LOCA is ensured. Therefore, the pressure/temperature exemption is not applied to these portions of piping.

Emergency Core Cooling (ECC) Function - Per Section 6.1 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 injection (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 exemp tion is not applied to these portions of piping.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 3 of 33 Rev. 1 Containment Heat Removal (CHR) Functi on - Per Section 4.8

.3 of the UFSAR, the RHR system also provides containmen t cooling so that condensation of the steam resulting from the blowdown due to the design basis LOCA is ensured.

Therefore, the pressure/temperature exemp tion is not applied to these portions of piping.

3. Open Ended Exemption

The open ended exemption is applied to:

1E11-RHR piping from MOV 1E11-F027A through the Torus Spray Header. 1E11-RHR piping from MOV 1E11-F027B through the Torus Spray Header. 1E11-RHR piping from MOV 1E11-F021A through the Drywell Spray Header. 1E11-RHR piping from MOV 1E11-F021B through the Drywell Spray Header.

By system, the above exemptions were applied as follows:

1. 1C11 Control Rod Drive (CRD) System (See Boundary Diagram HB-16064 and HB-16065) - The Class 2 portion of this system is less than 4" in diameter and exempt from examination, except for the 8" Scram Discharge 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, and then only to a pressure far below de sign pressure". This position has been continued through the 1 st , 2 nd and 3 rd 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 reported as augmented exams, not Code exams.

2. 1C41- Standby Liquid Control (SLC) System (See Boundary Diagram HB-16061). All components are exempt from examination because all piping is 4" NPS and less in diameter.

3. 1C71 Reactor Protection System (See Boundary Diagram HB-16568). All components are exempt from examination be cause all piping is 4" NPS and less in diameter.

4. 1E11 Residual Heat Removal (RHR) System (See Boundary Diagrams HB-16329&30) -This system has ECC, CHR, and reactor residual heat removal functions; therefore, the pressure/temperature exem ption cannot be applied. The exemptions applied to this piping are:

All components are exempt from exam ination on piping 4" NPS and less in diameter.

The open ended Spray Header piping downstream of E11-F027A&B and E11-F021A&B is exempt from examination.

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

5. 1E21 Core Spray (CS) System (See Boundary Diagrams HB-16328 and HB-16331). This system has ECC and CHR functions; therefore, the pressure/temperature exemption cannot be applied. There is not any open-ended piping; therefore, the only exemption is the 4" NPS and less size exemption.

6. 1E41 High Pressure Coolant Injection (HPCI) System (See Boundary Diagrams HB-16332&33). This system has an ECC function; therefore, the pressure/temperature exemption cannot be applied. It is SNC's position 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. 1E51 Reactor Core Isolation Cooling (See Boundary Diagrams HB-16334&35). Per the boundary Diagrams, only the portion of RCIC associated with containment boundaries or that connects on to other Cl ass 2 piping is classified as Class 2.

Per Section 4.7 of the UFSAR, the function of this system is to provide core cooling during reactor shutdown by pumping makeup water into th e reactor pressure vessel (RPV) in case of a loss of flow from the main feed system and is activated in time to preclude conditions which lead to inadequate core cooling. 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:

The 6" portion of pump suction piping (9 welds) from the Torus connection out to valve 1E51-F031. This piping is potentially subject to temperatures greater than 200 0F during accident conditions; therefore, the pressure and temperature exemption cannot be applied. Sin ce the size exemption and open-ended exemption cannot be applied, these 8 we lds (designated as 1E51-2RCIC-6-TS-2 through 9) 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 10"steam exhaust line from the Torus connection to the Turbine Discharge.

This piping (which includes welds 1E51-2RCIC-10-TD-23 thru 27 and weld 1E51-2RCIC-8-TD-1) is subject to temperatures greater than 200 0 F; 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 environment on 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 HBD, Schedul e 40 piping which is 0.365" (10") and 0.322" (8") thick and not subject to examination, but is part of the total number of non-exempt welds.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 5 of 33 Rev. 1 For the above listed Class 2 pi ping, none is subject to exam ination (however, they are listed 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. 1G41 Fuel Pool Cooling System (See Boundary Diagram HB-16002). There are no Class 2 components in the 1G41 system. The Class 2 inter-tie to RHR is shown on RHR drawing HB-16329.

9. 1G51 Torus Drain (See Boundary Diagram HB-16135) - This system provides no safety function except as containment functi on. However, since it is connected to the Torus it may see an elevated temperatur e during accident c onditions. The open-ended exemption cannot be used since the pi ping contains water; therefore, only the size exemption may be used.

10. 1N11 Main System (See Boundary Diagrams HB-11601and HB-11602 and the Class 2 portions of the Nuclear Boiler System Boundary Diagrams HB-16062 and HB-16063). 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 exemption applied to this pipi ng is the 4" NPS and less size exemption.

11. 1N37 Bypass Steam System (See Boundary Diagram HB-11018). 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. 1P41 Plant Service Water System (PSW) (See Boundary Diagram HB-16011). Per Boundary Diagram HB-16011, the piping from the containment isolation valves, the piping through the penetration, and the piping inside containment are Class 2.. The function of this piping is to provide cooling water to the drywell fan coil units, which per Section 5.2.2.7 of the UFSAR performs no active safety-related function. This piping is classified as safety related only to support the containment isolation safety-related function. This is not an RHR, E CC, or CHR function; therefore, the size exemption and pressure/temperature exemption may be used where applicable.

However, Page 10.7-7 of the FSAR while the equipment is not required for emergency conditions, the normal LOCA valve lineup has flow through this equipment. Therefore, as a conservatism, the pressure/temperature exemption will not strictly be used on the larger diam eter piping in the drywell even though permissible). This piping is represented by Isometric Sketches B-101, B-102, B-103, B-104, B-105, and B-106. Inclusion of these lines will be considered to add 50 non-exempt welds (but thin-wall) to the C-F-2 scope that will add about 4 addition examinations to the scope of C-F-2. The remainder of piping and components in the drywell is exempt on size.

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

13. 1P42 Reactor Building Closed Cooling Water (RBCCW) System (See Boundary Diagram HB-16009). Per Boundary Diagram HB-16009, the piping from the containment isolation valves, the piping th rough the penetration, a nd the piping inside containment are designated as Class 2 because of the containment function. This piping provides cooling water to the reactor recirculation pump motor bearings. Per Section 10.5.3 of the UFSAR, operation of the RBCCW system is not vital to safe shutdown of the plant under normal or accident conditions, an d failure of any component of this system will not cause a significant release of radioactivity. 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.

14. 1T48 Containment Purge and Inerting (See Boundary Diagram HB-16000 and HB-16024). Per Boundary Diagram HB-16000 and HB-16024, the piping from the containment penetration to the second containment isolation valve is designated as Class 2 because of the containment function.

The balance of the piping is not within the ISI scope. However, since heat may be removed from the containment by this system, it was considered as having a CHR function and the pressure and temperature exemption was not used. Much of this piping could be exempted using the open-ended exemption and should be evaluated. 15. 1T48 Drywell to Torus Differential Pressure System - (See Boundary Diagram HB-16153). (Note: The piping shown on HB-16153 is the same piping shown on HB-16024. See the P&ID for the actual configuration). This system connects to existing 1T48 containment penetrat ion piping shown on HB-16024 or HB-16153 downstream of the second containment isolat ion valve which is outside the scope of ISI. 16. 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 (PT) exemption applied. The applicable containment penetrations, their function, the Boundary Diagram, and the size are listed below:

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 7 of 33 Rev. 1 Containment Isolation Piping Penetration Description Drawing Dia Evaluation X-18 Radwaste HB-16176 3" Exempt-Size X-19 Radwaste HB-16176 3" Exempt-Size X-21 Service Air HB-16013 2" Exempt-Size X-22 Drywell Pneumatic HB-16299 2" Exempt-Size X-27A Fission Prod. Mon HB-16173 1" Exempt-Size X-27C,D Reactor Protection HB-16330 1" Exempt-Size X-27E Purge & Inerting HB-16024 1" Exempt-Size X-27F Drywell Pneumatic HB-16299 2" Exempt-Size X-28 Recirc Sample HB-16066 3/4" Exempt-Size X-28F H 2 O 2 Sample HB-16276 1" Exempt-Size X-31D H 2 O 2 Sample HB-16276 1" Exempt-Size X-31F Pump Seal Purge HB-16066 3/4" Exempt-Size X-33D Fission Prod. Mon HB-16173 1" Exempt-Size X-34E H 2 O 2 Sample HB-16276 1" Exempt-Size X-45C,D Drywell Pressure HB-16329 1" Exempt-Size X-35A-D TIP Drive HB-16561 <4" Exempt-Size X-35E TIP N 2 Purge HB-16561 1" Exempt-Size X-40C-F Drywell Pneumatic HB-16286 1" Exempt-Size X-45E Purge & Inerting HB-16024 1" Exempt-Size X-45F ILRT HB-16060 1" Exempt-Size X-46 Dem. Water HB-16015 4" Exempt-Size X-59A Pump Seal Purge HB-16066 3/4" Exempt-Size X-206A,B,C,D Purge & Inerting HB-16024 1" Exempt-Size X-209A,B,C,D Purge & Inerting HB-16024 1" Exempt-Size X-216A,B,C,D Purge & Inerting HB-16024 1" Exempt-Size X-217 H 2 O 2 Sample HB-16276 1" Exempt-Size X-223A(A-F) Vacuum Breakers HB-16024 1" Exempt-Size X-223B(A-F) Vacuum Breakers HB-16024 Exempt-Size

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc 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 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.

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

(Note: See Volume 1 for listing of Relie f 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 review.

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

For carbon steel piping, chlorides are not a issu

e. During 30 years of Inservice Inspection of Class 2 components, outside attack of Class 2 components has not been identified.

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

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 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc 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 Table 2-1 for information purposes only.

3 rd Interval There are two Class 2 vessels at Hatch - the RHR Heat Exchangers. Per Table IWC-2500-1, Category C-A of the 1989 Code only the number of welds on one of the two heat exchangers need to be volumetrically examined (three total). (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:

Two circumferential shell we lds at a structural discontinuity (Item C1.10). One head-to-shell weld (Item C1.20). Tubesheet-to-shell welds (Item C1.30). Not applicable to Hatch because the tubesheet is flanged in.

The HNP-1 Category C-A examinations are shown below:

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 1E11\2HX-A-1 Shell Head To Upper Shell Ring B-1 1991 2002 Limited coverage due to brackets.

See RR-5. C1.10 1E11\2HX-A-2 Upper Shell Ring To Lower Shell Ring B-1 C1.10 1E11\2HX-A-3 Lower Shell Ring To Flange B-1 C1.20 1E11\2HX-B-1 Shell Head To Upper Shell Rin g B-1 C1.10 1E11\2HX-B-2 Upper Shell Ring To Lower Shell Ring B-1 1988 1999 C1.10 1E11\2HX-B-3 Lower Shell Ring To Flange B-1 1993 2006 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 10 of 33 Rev. 1 4th Interval

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

The HNP-1 Category C-A examinations are shown below:

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 1E11\2HX-A-1 Shell Head To Upper Shell Ring B-1 2002 1R25 Limited coverage due to brackets. C1.10 1E11\2HX-A-2 Upper Shell Ring To Lower Shell Ring B-1 C1.10 1E11\2HX-A-3 Lower Shell Ring To Flange B-1 C1.20 1E11\2HX-B-1 Shell Head To Upper Shell Rin g B-1 C1.10 1E11\2HX-B-2 Upper Shell Ring To Lower Shell Ring B-1 1999 1R23 C1.10 1E11\2HX-B-3 Lower Shell Ring To Flange B-1 2006 1R27 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc 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" inlet nozzle weld and the "B" Outlet nozzle weld were examined as shown in Table 2-2. An inlet nozzle inner radius examination was not performed because of an SNC interpretation that the configuration had a rounded corner instead of an actual inner radius configuration. The examinations are shown in Table 2-2 for information purposes only.

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 th at only the nozzles on one of the two heat exchangers be examined. (Alternately the number of nozzles on one heat exchanger may be distributed over two heat exchangers). The nozzles initially selected for examination shall be re-examined over the life of the heat exchangers. Because 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 configuration. However, a 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 configuration, the Code figures are representative figures and it was not the intent of the Section 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 c onservative approach will be used for the 3 rd Interval. The examinations will be attempted and if a meaningful examination cannot be performed, relief will be requested.

However, as shown in Table 2-2, the 3 rd Interval examinations will be performed significantly more than 10-years after the previous examinations. This situation is evaluated below.

The previous determination that there was not an inner radius (therefore no examinations were required) is considered a less conservative application of engineering judgment, than presently being used. However, when the 3 rd Interval examinations are completed during 1R22, if there is no cracking, the structur al integrity of the noz zle inner radii will HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 12 of 33 Rev. 1 be verified for both the 2 nd and 3rd Intervals. Therefore, there will not be a technical or safety issue. The basis for this determinati on is that if they are not cracked during 1R22, then they were not cracked during the 2 nd Interval. Licensing will determine if this situation is reportable. Examinations are shown below:

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 1E11\2HX-A-I Inlet Nozzle B-1A 1988 1999 C2.22 1E11\2HX-A-I-IRS Inlet Nozzle Inner Radius B-1A 2000 (Surface Exam) 1R22 C2.21 1E11\2HX-A-O Outlet Nozzle B-1A C2.22 1E11\2HX-A-O-IRS Outlet Nozzle Inner Radius B-1B C2.21 1E11\2HX-B-I Inlet Nozzle B-1B C2.22 1E11\2HX-B-I-IRS Inlet Nozzle Inner Radius B-1B C2.21 1E11\2HX-B-O Outlet Nozzle B-1B 1991 2002 C2.22 1E11\2HX-B-O-IRS Outlet Nozzle Inner Radius B-1B 1R22 Number of 3 rd Interval Examinations and Cumulative Percentage 1 (25%)2 (50%) 4 (100%)

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 13 of 33 Rev. 1 4th Interval

The HNP-1 Category C-B examinations are shown below:

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 1E11\2HX-A-I Inlet Nozzle B-1A 1999 1R23 C2.22 1E11\2HX-A-I-IRS Inlet Nozzle Inner Radius B-1A 1R22 1R27 C2.21 1E11\2HX-A-O Outlet Nozzle B-1A C2.22 1E11\2HX-A-O-IRS Outlet Nozzle Inner Radius B-1B C2.21 1E11\2HX-B-I Inlet Nozzle B-1B C2.22 1E11\2HX-B-I-IRS Inlet Nozzle Inner Radius B-1B C2.21 1E11\2HX-B-O Outlet Nozzle B-1B 2002 1R25 C2.22 1E11\2HX-B-O-IRS Outlet Nozzle Inner Radius B-1B 1R22 1R27 Number of 4th Interval Examinations and Cumulative Percentage 1 (25%)2 (50%) 4 (100%)

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc 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. Relief Request RR-4 was superseded via the endorsement of Code Case N-509 in Revision 12 to Regulatory Guide 1.147. Revision 13 subseque ntly 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 the following table, 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. 1E11\2HX-A-USC-4 was examined in the 2nd Period (1R20).

CATEGORY C-C, ITEM C3.10 PRESSURE VESSEL WELDED ATTACHMENTS Component ISI Figure I3/P1 I3/P2 I3/P3 Comments 1E11\2HX-A-LSC-1 B-1 1E11\2HX-A-USC-1 B-1 1E11\2HX-A-USC-2 B-1 1E11\2HX-A-USC-3 B-1 1E11\2HX-A-USC-4 B-1 1R20 One welded attachment on one vessel required to be examined per Code Case N-509 1E11\2HX-B-LSC-1 B-1 1E11\2HX-B-USC-1 B-1 1E11\2HX-B-USC-2 B-1 1E11\2HX-B-USC-3 B-1 1E11\2HX-B-USC-4 B-1 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc 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 use in Revision 12 of Reg. Guide 1.147, 10% of the piping attachments must be examined.

There are 214 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 22 sets of welded attachme nts is required. Seven sets of welded attachments (32%) were examined during the 1 st Period, 11 sets during the 2 nd Period (cumulative percentage of 79%), and 6 sets during the 3 rd Period (Cumulative percentage of 100%). Note that the 2 nd Period is slightly in excess of the Code requirement of 75%. This was a result of the movement of augmen ted supports originally included in this scope that were moved. There is no effect on the quality of examinations.

Note: A review of the Indication Notification Forms for the 3 rd Interval did not identify any cases requiring additional examinations 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. 1 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 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 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 16 of 33 Rev. 1 4 th Interval Table IWC-2500-1, Category C-C of the 2001 Ed ition of ASME Section XI through the 2003 Addenda defines the examination require ments for Class 2 integrally welded attachments. These requirements mirror t hose in Code Case N-509 used during the 3 rd Interval.

Item C3.10 - Pressure Vessels -

As shown in the following table, 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. 1E11\2HX-A-USC-4 was examined in the 2nd Period (1R20) of the 3 rd Interval and will be re-examined during the 2 nd Period of the 4 th Interval..

CATEGORY C-C, ITEM C3.10 PRESSURE VESSEL WELDED ATTACHMENTS Component ISI Figure I3/P1 I3/P2 I3/P3 Comments 1E11\2HX-A-LSC-1 B-1 1E11\2HX-A-USC-1 B-1 1E11\2HX-A-USC-2 B-1 1E11\2HX-A-USC-3 B-1 1E11\2HX-A-USC-4 B-1 1R26 One welded attachment on one vessel required to be examined.

1E11\2HX-B-LSC-1 B-1 1E11\2HX-B-USC-1 B-1 1E11\2HX-B-USC-2 B-1 1E11\2HX-B-USC-3 B-1 1E11\2HX-B-USC-4 B-1 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 17 of 33 Rev. 1 Item C3.30 (Pumps) and C3.40 (Valves)

None Identified

Item C3.20 - Piping - There are 214 sets of non-exempt welded attachments in the Class 2 scope, as shown in Schedule Works. For the purpose of this discus sion, a set is a group of welded attachments associated with a sp ecific location. For in stance, a hanger clamp may have four welded lugs but it is considered one set. When a set of welded attachments is selected for exam ination all of the welded attachments in that set should be examined.

A minimum of 22 sets of welded attachme nts is required. Seven sets of welded attachments (32%) will be examined during the 1 st Period, 8 sets during the 2 nd Period (cumulative percentage of 68%), and 7 sets during the 3 rd Period (Cumulative percentage of 100%).

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 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc 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 1 st , 2 nd , and 3 rd Intervals - Not Evaluated

4th Interval Table IWC-2500-1, Category C-F-2 of the 2001 Edition 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 include 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 weld count to which the 7.5% sample will be applied. Per the Code Compliance Scheduling Summary for C-F-2 welds there are 1103 welds in the population, requiring 82 examinations. Additionally, there are 50+ non-exempt Class 2 Plant Service Water welds in containment that ar e less than 3/8" thick. Even though these welds are not required to be examined they will count in the total welds by which the 7.5% number is calculated. About 4 extra welds would require to be examined. Using ScheduleWorks, there will be roundup which will more than account for 4 welds, so they will be ignored. For Ca tegory 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 requirements. Allowing all of the roundup would necessitate 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. Therefore as long as a minimum of the 82 exams plus the 4 additional exams (tot al of 86 welds) are performed per Code Case N-598, using the below listed proration requirements the Code requirements will be met. (Note: 89 we lds 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 in for each line size (e.g., 10", 12" and 16") to the degree practicable.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 19 of 33 Rev. 1 RHR - RHR has a total of 563 C-F-2 welds versus a total of 1107 total welds; therefore about 44 of the 87 welds need to be selected in RHR (more may be selected if desired). These 44 welds are pror ated through the line sizes as follows.

RHR Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 1E11 6" 13 (3%) 3 8" 0 0 14" 12 (3%) 1 16" 131 (28%) 12 20" 170 (36%) 15 24" 145 (31%) 13 471 44 CS - CS has a total of 159 C-F-2 welds vers us a total of 1107 welds; therefore about 12 of the 87 welds need to be selected in CS (more may be selected if desired). These 12 welds are prorated through th e line sizes as follows.

CS Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 10" 6 (5%) 0 Less than 1 weld required. None selected 12" 75 (57%) 7 14" 8 (6%) 1 16" 42 (32%) 4 131 12 HPCI - HPCI has a total of 149 C-F-2 welds versus a total of 1107 welds; therefore about 12 of the 87 welds need to be selected in HPCI (more may be selected if desired). These 12 welds are prorat ed through the line sizes as follows.

HPCI Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 10" 44 (32%) 3 12" 2 (1%) 0 Less than 1 weld required. None selected 14" 41 (30%) 3 16" 24 (18%) 2 18" 7 (5%) 1 20" 15 (11%) 2 24" 3 (2%) 1 136 12 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 20 of 33 Rev. 1 RCIC - RCIC has a total of 14 C-F-2 welds versus a total of 1107 welds; therefore about 1 of the 87 welds could be selected in RCIC. None were selected because all welds were less than 0.375" thick.

RCIC Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 10" 0 0 6" 0 0 8" 0 0 Torus Drainage (TDP) - TDP has a total of 10 C-F-2 welds versus a total of 1107 welds; therefore one or less of the 87 welds need to be selected in TDP. None were selected.

TDP Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 8" 10 (100%) 0 10 0 Main Steam (N11) - MS has a total of 91 C-F-2 welds versus a total of 1107 welds; therefore about 7 of the 87 weld s need to be selected in MS (more may be selected if desired). These 7 welds are prorated through the line sizes as follows.

MS Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 6" 6 (7%) 1 10" 4 (4%) 0 14" 6 (7%) 1 24" 75 (82%) 5 91 7 Auxiliary Steam (N37)

- This system has a total of 52 C-F-2 welds versus a total of 1107 welds; therefore about 4 of the 87 welds need to be selected (more may be selected if desired). These 4 welds are prorated through the line sizes as follows.

Aux Steam Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 16" 52 (100%) 4 52 4 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 21 of 33 Rev. 1 Torus Purge and Inerting (T48) - This system has a total of 65 C-F-2 welds versus a total of 1107 welds; therefor e about 5 of the 87 welds need to be selected in T48 (more may be selected if desired). These 5 welds are prorated through the line sizes as follows.

MS Line Size Number of Welds > 0.375" Prorated Number of Welds To Be Examined Comments 6" 1 (< 1%) 0 18" 28 (60%) 3 20" 18 (38%) 2 47 5

4. Footnote 2 indicates that this prorated number of weld examinations determined for each system as shown in the above table should then be distributed among terminal ends and structural discontinuities prorated, to the degree practicable, on the number of non-exempt terminal ends and struct ural discontinuities within a system.

Structural discontinuities in clude pipe weld joints to vessel nozzles, valve bodies, pump casings, pipe fittings (s uch as elbows, tees, reducers, flanges, etc.), and pipe branch connections and fittings. Term inal ends would be those structural discontinuities where a piping connects to structures, components, or pipe anchors

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

1E11 - RHR: Per Schedule Works there are 422 non-exempt welds with a wall thickness of 0.375" or thicker, and are not pi pe-to-pipe welds. Of these 422 welds, the following 18 welds (4.3% of the 422 welds) are considered terminal end welds (and the remainder are stru ctural discontinuities):

Piping Welds Connecting to the Torus

1E11-2RHR-24A-TS-A-1

1E11-2RHR-24A-TS-C-1

1E11-2RHR-24B-TS-B-1

1E11-2RHR-24B-TS-D-1

1E11-2RHR-16A-TL-2

1E11-2RHR-16B-TL-2

Piping Welds Connecting to Pump Nozzles 1E11-2RHR-16A-PD-A-1 1E11-2RHR-16A-PD-C-1

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

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

1E11-2RHR-24A-TS-A-17

1E11-2RHR-24A-TS-C-18 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 22 of 33 Rev. 1 1E11-2RHR-24B-TS-B-16 1E11-2RHR-24B-TS-D-17

Piping Welds Connecting to RHR Heat Exchanger Nozzles

1E11-2RHR-20A-HXI-3 1E11-2RHR-20A-HXO-1

1E11-2RHR-20B-HXI-3 2E11-2RHR-20B-HXO-1

Selecting approximately 4.3% of the 44 welds selected for examination as a terminal weld population yields a population of 1 to 2 terminal end welds to be examined. Terminal End 1E11-2RHR-16A-TL-2 was scheduled for examination. The remaining welds were all struct ural discontinuities.

1E21 - Core Spray - Per Schedule Works there are 121 non-exempt welds with a wall thickness of 0.375" or thicker, and are not pipe-to-pipe welds. Of these 121 welds, the following 4 welds (3.3% of the 121 welds) are considered terminal end welds (and the remainder are structural discontinuities):

Piping Welds Connecting to the Torus

1E21-2CS-16A-TS-2 (Note: weld TS-1 is in the IWE scope) 1E21-2CS-16B-TS-2 (Note: weld TS-1 is in the IWE scope)

Piping Welds Connecting to Pump Nozzles

1E21-2CS-12A-1 1E21-2CS-16A-TS-23 1E21-2CS-12B-1 1E21-2CS-16B-TS-22

Selecting approximately 3.3% of the 12 required welds as a terminal weld population yields 0 to 1 welds to be examined. Terminal End 1E21-2CS-16A-TS-2 was scheduled for examination.

1E41 - HPCI: Per Schedule Works there are 135 non-exempt welds with a wall thickness of 0.375" or thicker, and are not pi pe-to-pipe welds. Of these 135 welds, the following 8 welds (5.9% of the 135 welds) are considered terminal end welds (and the remainder are stru ctural discontinuities):

Piping Welds Connecting to the Torus

1E41-2HPCI-16-TS-2 (Note: weld TS-1 is in the IWE scope) 1E41-2HPCI-24-TD-3 (Note: weld TD-4 is in the IWE scope)

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 23 of 33 Rev. 1 Piping Welds Connecting to Pump Nozzles

1E41-2HPCI-10-R-1 (discharge)

1E41-2HPCI-14-PS-4 (suction) 1E41-2HPCI-12-PC-1 (booster pump connection) 1E41-2HPCI-12-PC-5 (booster pump connection)

Piping Welds Connecting to Turbine

1E41-2HPCI-18-TD-1

1E41-2HPCI-10-SS-37

Selecting approximately 5.9% of the 13 welds as a terminal weld population yields 0 to 1 welds to be examined. Terminal End 1E41-2HPCI-10-SS-37 was scheduled for examination.

1E51 - RCIC. There are no welds selected for examination.

1G51 - Torus Cleanup. There are no welds selected for examination.

1N11 - Main Steam Auxiliary. Per Schedule Works there are 78 non-exempt welds with a wall thickness of 0.375" or thicker, a nd are not pipe-to-pipe welds. Of these 78 welds, the following 4 welds (5.1% of the 78 welds) are considered terminal end welds (and the remainder are structural discontinuities):

1N11-2MSA-24A-1 and 17

1N11-2MSA-24B-1 and 18

1N11-2MSA-24C-1 and 19

1N11-2MSA-24D-1 and 16

Selecting approximately 5% of the 4 welds as a terminal weld population yields 0 to 1 weld to be examined. Terminal End 1N11-2MSA-24C-19 was scheduled for examination.

1N37 - Turbine Steam Bypass. Per Schedule Works there are 48 non-exempt welds with a wall thickness of 0.375" or thicker, a nd are not pipe-to-pipe welds. Of these 48 welds, the following 2 welds (4.1% of the 48 welds) are considered terminal end welds (and the remainder are structural discontinuities):

1N37-2TSB-16A-14

1N37-2TSB-16B-13

Selecting approximately 4% of the 4 welds as a terminal weld population yields 0 to 1 welds to be examined. No welds were scheduled for examination.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 24 of 33 Rev. 1 1T48 - Purge and Inerting. Per Schedule Works there are 46 non-exempt welds with a wall thickness of 0.375" or thicker, a nd are not pipe-to-pipe welds. Of these 46 welds, the following 4 welds (8.7% of the 48 welds) are considered terminal end welds (and the remainder are structural discontinuities):

Piping Welds Connecting to the Torus

2T48-2CPI-20-PIT-8A (Note: weld PIT-9 is in the IWE scope) 2T48-2CPI P0T-1

Piping Welds Dead-ending at the Vacuum Breakers

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

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

Selecting approximately 8.7% of the 5 welds as a terminal weld population yields 0 to 1 welds to be examined. Terminal End 2T48-2CPI-20A-VB-1 was scheduled for examination.

4 th Interval There are no substantial changes between the 1989 Code and the 2001 Edition with Addenda through 2003. Therefore, the weld selection is the same.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 25 of 33 Rev. 1 Category C-G Pressure Retaining Welds in Pumps and Valves Hatch 1 RHR Pump casings (1E11-C002A (B)(C)(D)) are cast st eel (ASTM A-216 GR. WCB), and do not contain welds, reference vendor manual S17351.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 26 of 33 Rev. 1 AUGMENTED EXAMINATIONS The NRC's safety evaluation dated 6/16/97 of the 3 rd Interval Program listed several augmented programs that will be maintained during the 4 th Interval.

The NRC's safety evaluation dated 6/16/97 of the 3 rd Interval Program stated that in addition to the 1989 Code required examinations, the examination of the Scram Discharge Volume (SDV) piping in accordance with NUREG-0803 would be performed.

NUREG-0803 contends that sin ce the SDV was designed and fa bricated in accordance with Class 2 piping that it should be subjected to the ISI requirements for Class 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-one (EBB, 0.5" thick, schedule 80 carbon steel), welds.

The 1974 Code required examination of 100% of welds 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 and 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 interval. The 1980 Code required a surface examination technique for 0.5" thick piping.

For the 3 rd and 4 th Interval, a 7.5% sample (volumetric) is required. Welds and examinations are shown in the following table. This piping is designated as "Class 2S" in Schedule Works.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 27 of 33 Rev. 1 AUGMENTED CRD EXAMINATIONS Component I3/P1 I3/P2 I3/P3 I4/P1 I4/P2 I4/P3 1. 1C11-2CRD-8N-SDV-1

2. 1C11-2CRD-8N-SDV-2

3. 1C11-2CRD-8N-SDV-2A

4. 1C11-2CRD-8N-SDV-2B

5. 1C11-2CRD-8N-SDV-2C

6. 1C11-2CRD-8N-SDV-3

7. 1C11-2CRD-8N-SDV-4 1R19- 1R24 8. 1C11-2CRD-8N-SDV-6

9. 1C11-2CRD-8N-SDV-7

10. 1C11-2CRD-8N-SDV-8

11. 1C11-2CRD-8N-SDV-9

12. 1C11-2CRD-8N-SDV-10

13. 1C11-2CRD-8N-SDV-11 -1R17- 1R23 14. 1C11-2CRD-8N-SDV-12 1R21- 1R26 15. 1C11-2CRD-8N-SDV-13

16. 1C11-2CRD-8S-SDV-1

17. 1C11-2CRD-8S-SDV-2

18. 1C11-2CRD-8S-SDV-2A

19. 1C11-2CRD-8S-SDV-3

20. 1C11-2CRD-8S-SDV-4

21. 1C11-2CRD-8S-SDV-5

22. 1C11-2CRD-8S-SDV-6

23. 1C11-2CRD-8S-SDV-7

24. 1C11-2CRD-8S-SDV-8

25. 1C11-2CRD-8S-SDV-9

26. 1C11-2CRD-8S-SDV-10

27. 1C11-2CRD-8S-SDV-11

28. 1C11-2CRD-8S-SDV-12

29. 1C11-2CRD-8S-SDV-13

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 28 of 33 Rev. 1 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. 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 ISI Program indicates that the portion of thin-w all, 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-E CCS, non-RHR, or non-CHR function.

Per pipe schedule tables, this thin wall piping is limited to Sc hedule 40 (or thinner) piping 6", 8", or 10" in diameter discharge piping in RHR and CS. The following table shows the Class 2 welds in the thin wa ll scope and defines the welds that do not meet criteria (a) or criteria (b).

There are approximately 62 welds that meet criteria (a( or criteria (b); therefore, at least five welds are required to be examined to meet the 7.5% requirement. Within the required scope, five were examined and the requirements were met.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 29 of 33 Rev. 1 THIN-WALL PIPING AUGMENTED EXAMINATIONS Weld Fig I3/P1 I3/P2 I3/P3 I4/P1 I4/P2 I4/P3 1. 1E11-2RHR-6A-DS-1 B-52 2. 1E11-2RHR-10A-DS-1 B-52 3. 1E11-2RHR-10A-DS-2 B-52 4. 1E11-2RHR-6A-TSP-1 B-63 5. 1E11-2RHR-6A-TSP-2 B-63 6. 1E11-2RHR-6A-TSP-3 B-63 7. 1E11-2RHR-6A-TSP-4 B-63 8. 1E11-2RHR-6A-TSP-5 B-63 9. 1E11-2RHR-6A-TSP-6 B-63 10. 1E11-2RHR-6A-TSP-7 B-63 11. 1E11-2RHR-6A-TSP-8 B-63 12. 1E11-2RHR-6A-TSP-9 B-63 13. 1E11-2RHR-6A-TSP-10 B-63 14. 1E11-2RHR-6A-TSP-11 B-63 15. 1E11-2RHR-6A-TSP-12 B-63 16. 1E11-2RHR-6B-DS-1 B-62 17. 1E11-2RHR-10B-DS-1 B-62 18. 1E11-2RHR-10B-DS-2 B-62 19. 1E11-2RHR-10B-DS-3 B-62 20. 1E11-2RHR-6B-TSP-1 B-65 21. 1E11-2RHR-6B-TSP-2 B-65 22. 1E11-2RHR-6B-TSP-3 B-65 23. 1E11-2RHR-6B-TSP-4 B-65 24. 1E11-2RHR-6B-TSP-5 B-65 25. 1E11-2RHR-6B-TSP-6 B-65 26. 1E11-2RHR-6B-TSP-7 B-65 27. 1E11-2RHR-6B-TSP-8 B-65 1R18 1R23 28. 1E11-2RHR-6B-TSP-9 B-65 29. 1E11-2RHR-6B-TSP-10 B-65 30. 1E11-2RHR-8-FPD-1 B-71 1R22 1R27 31. 1E11-2RHR-8-FPD-2 B-71 1R22 1R27 32. 1E11-2RHR-8-FPD-3 B-71 33. 1E11-2RHR-8-FPD-4 B-71 34. 1E11-2RHR-8-FPD-5 B-71 35. 1E11-2RHR-10A-SWDS-1 B-48 36. 1E11-2RHR-10A-SWDS-2 B-48 37. 1E11-2RHR-10A-SWDS-3 B-48 38. 1E11-2RHR-10A-SWDS-4 B-48 39. 1E11-2RHR-10A-SWDS-5 B-48 1R18 1R23 40. 1E11-2RHR-10A-SWDS-6 B-48 41. 1E11-2RHR-10A-SWDS-7 B-48 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 30 of 33 Rev. 1 THIN-WALL PIPING AUGMENTED EXAMINATIONS Weld Fig I3/P1 I3/P2 I3/P3 I4/P1 I4/P2 I4/P3 42. 1E11-2RHR-10A-SWDS-8 B-48 43. 1E11-2RHR-10A-SWDS-9 B-48 44. 1E11-2RHR-10A-SWDS-10 B-48 45. 1E11-2RHR-10A-SWDS-11 B-48 46. 1E11-2RHR-10A-SWDS-12 B-48 47. 1E11-2RHR-10B-SWDS-1 B-60 48. 1E11-2RHR-10B-SWDS-2 B-60 49. 1E11-2RHR-10B-SWDS-3 B-60 50. 1E11-2RHR-10B-SWDS-4 B-60 1R20 1R25 51. 1E11-2RHR-10B-SWDS-5 B-60 52. 1E11-2RHR-10B-SWDS-6 B-60 53. 1E11-2RHR-10B-SWDS-7 B-60 54. 1E11-2RHR-10B-SWDS-8A B-60 55. 1E11-2RHR-10B-SWDS-9A B-60 56. 1E11-2RHR-10B-SWDS-10 B-60 57. 1E11-2RHR-10B-SWDS-11 B-60 58. 1E11-2RHR-10B-SWDS-12 B-60 59. 1E21-2CS-10A-1 B-6 60. 1E21-2CS-10A-2 B-6 61. 1E21-2CS-10A-3 B-6 62. 1E21-2CS-10B-1 B-9 63. 1E21-2CS-10B-2 B-9 64. 1E21-2CS-10B-3 B-9 65. 1E21-2CS-10B-4 B-9 65 TOTAL WELDS 5 WELDS REQUIRED 2 1 2 2 1 2 HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 31 of 33 Rev. 1 THIN-WALL PIPING NOT IN THE EXAMINATION COMMITMENT TO THE NRC Weld Fig. Basis for Not Including in the Thin-Wall Examination Scope1E11-2RHR-6A-RVD-1 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-2 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-3 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-4 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-5 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-6 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-7 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-8 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-9 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-10 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-11 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-12 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-13 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-14 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-15 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-16 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-17 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-18 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6B-RVD-1 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-2 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-3 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-4 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-5 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-6 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-7 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-8 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-9 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-10 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-11 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-12 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-13 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-14 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-15 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-16 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-17 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-18 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-19 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-20 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-8-FPS-7 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-8 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-9 B-72 Suction Piping - Not Required

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 32 of 33 Rev. 1 THIN-WALL PIPING NOT IN THE EXAMINATION COMMITMENT TO THE NRC Weld Fig. Basis for Not Including in the Thin-Wall Examination Scope1E11-2RHR-8-FPS-10 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-11 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-12 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-13 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-14 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-15 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-16 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-17 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-18 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-19 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-20 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-21 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-22 B-72 Suction Piping - Not Required 1E21-2CS-10A-TL-1 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-2 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-3 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-4 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-5 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-6 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-7 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-8 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-9 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-10 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-11 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-12 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-13 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-1 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-2 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-3 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-4 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-6 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-7 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-8 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-9 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-10 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-11 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-12 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-13 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-14 B-8 Isolable Test Line - Not ECC, RHR, or CHR

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 2 COMPONENTS Hatch 1 Basis Doc-Class 2.doc Page 33 of 33 Rev. 1 Additionally, portions of the Reactor Core Isolation Cooling are designated as Class S on Boundary Diagram HB-16334 and HB-16335. It will be treated using 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 St orage 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, examin ation of piping welds and integrally welded attachments in not required.

6" Suction Line from valve 1E51-F031 through valve 1E51-F029 (Designated as 1E51-2RCIC-6TS-10, 11, 12, 13, and 14 on Fi gure 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 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. (Not shown in Schedule Works).

4" (and less) Steam Supply - This piping is size exempt; therefore, examination of piping welds and integrally welded attachments in 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 examination of the piping welds. The welded attachments on this line are subject to Category "CC" type exams and are shown in the following table. 1E51-2RCIC-10-TD-12PS-1 (25% sample) was examined during the 3 rd Period. These attachments are designated as Category CC-R in Schedule Works.

Class S "Non-Exempt" RCIC Integrally Welded Attachments Welded Attachment Fig I3/P1 I3/P2 I3/P3 Support 1. 1E51-2RCIC-10-TD-10PS-1 AND 2 B-24 E51-RCSEH-3

2. 1E51-2RCIC-10-TD-12PS-1 B-24 C E51-RCSEH-719

3. 1E51-2RCIC-10-TD-14PS-1 THRU 4 B-25 E51-RCSEH-4

4. 1E51-2RCIC-10-TD-4PL-1 THRU 4 B-24 E51-RCSEH-714

200 k55 ?5? iuL" 00 'n N P gg SS w -N -- w -N w vl 8 oso s s gsg --0 'n - ~8 'n 68 ggs 'n4 qOg s52s '02 -GS OPP 0 0, so0 ss -22 8 88 s $ s g 1 o 8 rn o D V, rn rn B c 5 =! 0 Z E 2 gg zrn ; 5 ;El 8 b CZ g? ;El sg 0 rn -I x 0 Dl 5 $ 0 0 c Z I rn* "0 z 2 gg ;El sf 0 o g Z I rn

• mo e2 g? ;II sg 0 o 0 c Z I QD zz 8? 3 sf 0 Southern Nuclear Operating Company Page I - 113012006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 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 1 100.00% 100% 0 0.00% 0% 1 50% 50% ACTUAL ROUND COUNT PERIOD UP 0 100.00%

100% 2 100 00% 100% 2 100% 100%

Southern Nuclear Operating Company Page I - 1/30/2006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS C-C C3.10 10 10% 1 1 1 C-C C3.20 210 10% 2 1 21 21 Total: 220 22 22 22 ACTUAL ROUND COUNT PERIOD UP 0 0% 0% 6 28.57% 29% 6 27.20% 28% ACTUAL ROUND COUNT PERIOD UP 1 100.00% 100% 8 66.67% 67% 9 68.10% 69% ACTUAL ROUND COUNT PERIOD UP 0 100.00% 100% 7 100.00% 100% 7 100% 100%

Southern Nuclear Operating Company Page I - 113012006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS C-F-2 C5.51CPI 63 7.50% 4.73 5 6 C-F-2 C5.51 CS 157 7.50% 1 1.78 12 13 C-F-2 3.51 HPCI 147 7.50% 11.03 12 13 C-F-2 C5.51 MS 89 7.50% 6.68 7 6 C-F-2 3.51 RCIC 14 0% 0 0 0 C-F-2 C5.51RHR 534 7.50%

40.05 41 46 C-F-2 C5.51TDP 10 7.50% 0.75 1 0 C-F-2 C5.51TSP 48 7.50% 3.6 4 4 C-F-2 C5.81CPI 2 7.50% 0.15 1 0 C-F-2 C5.81 CS 2 7.50% 0.15 1 0 C-F-2 X.81HPCI 2 7.50% 0.15 1 0 C-F-2 C5.81MS 2 7.50% 0.15 1 1 C-F-2 C5.81 RHR 29 7.50% 2.18 3 0 C-F-2 C5.81 TSB 2 7.50% 0.15 1 0 C-F-2 C5.81TSP 2 7.50% 0.15 1 0 Total: 1103 82 91 89 PERIOD 2 ACTUAL ROUND COUNT PERIOD UP 1 84.57% 80% 4 59.42% 59% 2 72.53% 67% 3 59.88% 58% 0 0% 0% 19 84.89% 83% 0 0.00% 0% 1 83.33% 75% 0 0.00% 0% 0 0.00% 0% 0 0.00% 0% 0 666.67%

100% 0 0.00% 0% 0 0.00% 0% 0 0.00% 0% 30 74.30% 67% PERIOD 1 ACTUAL ROUND COUNT PERIOD UP 3 63.42% 60% 3 25.47% 25% 6 54.40% 50% 1 14.97% 15% 0 0% 0% 15 37.45% 37% 0 0% 0% 2 55.56% 50% 0 0% 0% 0 0% 0% 0 0% 0% 1 666.67%

100% 0 0% 0% 0 0% 0% 0 0% 0% 31 37.80% 34% PERIOD 3 ACTUAL ROUND COUNT PERIOD UP 2 126.85% 120% 6 110.36% 109% 5 117.86% 109% 2 89.82% 86% 0 0% 0% 12 114.86%

113% 0 0% 0% 1 111.11% 100% 0 0% 0% 0 0% 0% 0 0% 0% 0 666.67%

100% 0 0% 0% 0 0% 0% 0 0% 0% 28 108.00% 98%

Revision:

1 Category, ItemNO. HNP-1 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company Period 1 Iso No. Comp. Desc. Scope I Method I Procedure Code Case C A HI 1 El 1-2HX-A-1 8-32 C1.20 1 El 1 -2HX-A-1 SHELL HEAD TO UPPER SHELL RlNG AUG 2 El 1 OWN PRE C -A H1 1 El 1 -2HX-A-2 6-32 IS1 C1.10 1 El 1 -2HX-A-2 RING AUG 2 El 1 OWN PRE C -A HI 1 El 1 -2HX-A-3 6-32 IS\ C1.10 1 El 1 -2HX-A-3 LOWER SHELL RING TO FLANGE AUG 2 El 1 OWN PRE C -A HI 1 El 1-2HX-6-1 6-32 IS1 C1.20 1 El 1 -2HX-6-1 SHELL HEAD TO UPPER SHELL RlNG AUG 2 El 1 OWN PRE C -A HI 1 El 1 -2HX-6-2 ISIII 6-32 IS1 C1.10 1 El 1 -2HX-6-2 RING AUG 2 El 1 OWN PRE C -A HI 1 El 1-2HX-6-3 lSll/ 8-32 IS1 C1.10 1 El 1 -2HX-6-3 LOWER SHELL RING TO FLANGE AUG 2 Ell OWN PRE Page 1 - 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 1 - 1 111 812006 / Period 1 Period 2 Period 3 w r. 2 2 r,- I I - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -s-- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case C -B HI 1 El 1-2HX-A-I ISIII 8-32 IS1 C2.21 1 El 1 -2HX-A-I lSlil INLET NOZZLE TO RHR HX SHELL AUG 2 El 1 om PRE C -6 HI 1 El 1-2HX-A-I-IRS 8-32 IS1 C2.22 1 El 1 -2HX-A-I-IRS RHR HX INLETNOZZLE INNER RADIUS AUG 2 El I om PRE C -B HI 1 El 1 -2HX-A-0 8-32 IS\ C2.21 1 El 1 -2HX-A-0 RHR HXSHELLTO OUTLETNOZZLE AUG 2 El 1 om PRE C -B HI 1 El 1 -2HX-A-0-IRS 8-32 IS1 C2.22 1 El 1 -2HX-A-0-IRS RADIUS AIJG 2 El I om PRE C -B HI 1 El 1 -2HX-8-1 8-32 IS1 C2.21 1 El 1 -2HX-8-1 INLET NOZZLE TO RHR HX SHELL AUG 2 El 1 om PRE C -B HI 1 El 1-2HX-8-I-IRS 8-32 IS1 C2.22 1 El 1 -2HX-8-I-IRS RHRHXINLETNOZZLEINNERRADIUS AUG 2 El 1 om PRE C -B HI 1El1-2HX-8-0 8-32 IS1 C2.21 1 El 1 -2HX-8-0 RHRHXSHELLTOOUTLETNOZZLE AUG 2 El 1 om PRE C -B HI 1 El 1-2HX-8-0-IRS 8-32 IS1 C2.22 1 El 1 -2HX-8-0-IRS RADIUS AUG 2 El 1 OWN PRE N m (3 2 2 55 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - e Y) 2 2 $5 -s---------- - . - - - - - - - - - - ---------s-- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -----s------ - - - - - - - - - - - - - - - - - - - - - - - - - - - -

Revision:

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

Class Surnrnarv I CornplD I Svstern Scope I Method I Procedure Code Case LOWER SUPPORT BRACKET AUG OWN PRE C -C H1 1 El 1-2HX-A-USC-1 8-32 IS1 C3.10 1 El 1 -2HX-A-USC-1 UPPER SUPPORT BRACKET AUG 2 El 1 OWN PRE C -C HI 1 El 1-2HX-A-USC-2 8-32 IS1 C3.10 1 El 1 -2HX-A-USC-2 UPPER SUPPORT BRACKET AUG 2 El 1 OWN PRE C-C HI 1El1-2HX-A-USC-3 8-32 IS1 C3.10 1 El 1 -2HX-A-USC-3 UPPER SUPPORT BRACKET AUG 2 El 1 OWN PRE C -C HI 1 El 1-2HX-A-USC-4 8-32 IS1 C3.10 1 El 1 -2HX-A-USC-4 UPPER SUPPORT BRACKET AUG 2 El I OWN PRE C -C H1 1 El 1 -2HX-B-LSC-1 8-32 IS1 C3.10 1 El 1 -2HX-B-LSC-1 LOWER SUPPORT BRACKET AUG 2 El 1 OWN PRE C -C HI 1 El 1-2HX-B-USC-1 8-32 IS1 C3.10 1 El 1-2HX-B-USC-1 UPPER SUPPORT BRACKET AUG 2 El 1 OWN PRE C-C HI 1 El 1-2HX-B-USC-2 8-32 IS1 C3.10 1 El 1-2HX-B-USC-2 UPPER SUPPORT BRACKET AUG 2 El I OWN PRE C-C HI 1 El 1-2HX-B-USC-3 8-32 IS1 C3.10 1 El 1 -2HX-B-USC-3 UPPER SUPPORT BRACKET AUG 2 El 1 OWN PRE C -C HI 1 El 1-2HX-B-USC-4 8-32 IS1 UPPER SUPPORT BRACKET AUG OWN PRE Page 1 - 23 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 2 - 23 111 812006 1 Period 1 Period 2 Period 3 w h 2 2 I F I .- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - . - - - - - - - - . - - . - - - - . Category, Iso No. ItemNO, Cornp. Desc.

Scope I Method I Procedure Code Case Class Summary I ComplD I System C -C HI 1 El 1-2RHR-1OA-SWDS-1 PS-1 AND 2 8-48 IS1 C3.20 1 El 1 -2RHR-1 OA-SWDS-1 PS-1 AND 2 El 1-RHRH-64 AUG 2 El I ow PRE C -C H1 1El1-2RHR-lOA-SWDS-4PL-2 THRU 9 8-48 IS1 C3.20 1 El 1 -2RHR-1 OA-SWDS-4PL-2 THRU 9 El 1-RHRH-63 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-108-SWDS-1 PS-1 AND 2 8-60 IS1 C3.20 1 El 1 -2RHR-108-SWDS-1 PS-1 AND 2 El 1-RHRH-58 AUG 2 El 1 OWN pRE C -C H1 1 El 1-2RHR-108-SWDS-4PL-1 THRU 8 8-60 IS1 C3.20 1 El 1 -2RHR-1OB-SWDS-4PL-1 THRU 8 El 1-RHRH-57 AUG 2 El 1 ow pRE C -C HI 1El1-2RHR-16A-DS-14PS 8-52 1st C3.20 1 El 1 -2RHR-l6A-DS-14PS El 1-RHRH-144 AUG 2 El 1 om pRE C -C H1 1El1-2RHR-16A-DS-16PS-1 AND 2 8-52 IS1 C3.20 1 El 1 -2RHR-16A-DS-16PS-1 AND 2 El 1-RHRH-708 AUG 2 El 1 OWN PRE C-C HI 1 El 1 -2RHR-16A-DS-2PS 8-52 1st C3.20 1 El 1 -2RHR-16A-DS-2PS El 1-RHRH-235 AUG 2 El 1 OWN PRE C-C HI 1 El I-2RHR-16A-DS-7PS 8-52 IS1 C3.20 1 El 1 -2RHR-16A-DS-7PS El 1-RHRH-236 AUG 2 El 1 om PRE C -C HI 1 El 1-2RHR-16A-HXI-7PL-2 THRU 5 8-44 IS1 C3.20 1 El 1 -2RHR-16A-HXI-7PL-2 THRU 5 El 1-RHRH-39 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-16A-HXO-4PL-1 THRU 4 8-47 IS1 C3.20 1 El 1 -2RHR-16A-HXO-4PL-1 THRU 4 El 1-RHRH-42 AUG 2 El 1 OWN PRE CY m ~3 2 2 I I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - d U, 2 2 I I -----------. - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------S--- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - . ------------ - - - - - - - - - - - - ----.------- - - - - - - - - . - - -

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1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 3 - 23 111 812006 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 HI 1 El 1-2RHR-16A-HXO-5PS 6-47 IS1 C3.20 1 El 1 -2RHR-16A-HXO-5PS El 1-RHRH-225 AUG 2 El I OWN PRE C -C HI 1 El 1-2RHR-16A-SH-15PS-1 AND 2 6-5 1 IS1 C3.20 1 El 1 -2RHR-16A-SH-15PS-1 AND 2 El 1-RHRH-244 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-l6A-SH-5PS 6-5 1 IS1 C3.20 1 El 1 -2RHR-16A-SH-5PS El 1 -RHRH-248 AUG 2 El 1 OWN PRE C-C H1 1 El 1-2RHR-166-DS-6PL-1 THRU 8 6-62 IS1 C3.20 1 El 1 -2RHR-166-DS-6PL-1 THRU 8 El 1-RHRH-240 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-166-HXI-3PS-1 THRU 4 6-55 IS1 C3.20 1 El 1 -2RHR-16B-HXI-3PS-1 THRU 4 El 1-RHRH-411 AUG 2 El I OWN PRE C -C Hl 1 El 1-2RHR-166-HXI-6PL-2 THRU 5 6-55 IS1 C3.20 1 El 1 -2RHR-166-HXI-6PL-2 THRU 5 El 1-RHRH-30 AUG 2 El 1 OWN PRE C -C H1 1El1-2RHR-16B-HXI-7PL-1 AND 2 8-55 IS1 C3.20 1 El 1-2RHR-166-HXI-7PL-1 AND 2 El 1-RHRH-213 AUG 2 El I OWN PRE C -C HI 1 El 1-2RHR-166-HXO-3PS 6-58 IS1 C3.20 1 El 1 -2RHR-166-HXO-3PS El 1-RHRH-33 AUG 2 El I OWN PRE C -C HI 1 El 1-2RHR-166-HXO-4PS B-58 IS1 C3.20 1 El 1 -2RHR-166-HXO-4PS El 1-RHRH-218 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-166-SH-15PS-1 AND 2 B-61 IS1 C3.20 1 El 1-2RHR-166-SH-l5PS-1 AND 2 El 1-RHRH-250 AUG 2 El 1 OWN PRE Revision:

1 HNP-1 Third Interval Class 2 ISI Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I CornplD I System Scope I Method I Procedure Code Case C -C HI 1 El 1-2RHR-166-SH-5PS 6-6 1 IS1 C3.20 1 El 1 -2RHR-166-SH-5PS El 1-RHRH-66 AUG 2 El 1 OWN PRE C -C HI 1 El 1 -2RHR-20A-BP-1 PL-1 THRU B 8-49 IS1 C3.20 1 El 1 -2RHR-20A-BP-1 PL-1 THRU 8 El 1-RHRH-222 AUG 2 El 1 OWN PRE C-C HI 1 El 1-2RHR-20A-BP-1 PS-1 6-49 IS1 C3.20 1 El 1 -2RHR-20A-BP-1 PS-1 El 1-RHRH-221 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-20A-D-1 PS-1 AND 2 6-34 IS1 C3.20 1 El 1-2RHR-20A-D-1 PS-1 AND 2 El 1-RHRH-350 AUG 2 El 1 OWN PRE C -C HI 1 El 1 -2RHR-20A-D-1 PS-3 AND 4 6-34 IS1 C3.20 1 El 1 -2RHR-20A-0-1 PS-3 AND 4 El 1-RHRH-317 AUG 2 El 1 OWN PRE C -C H1 1 El 1-2RHR-20A-D-1 PS-5 6-34 IS1 C3.20 1 El 1 -2RHR-20A-D-1 PS-5 El 1-RHRH-19 AUG 2 El 1 OWN PRE C -C HI 1 El 1 -2RHR-20A-D-5PS-1 8-34 IS1 C3.20 1 El 1 -2RHR-20A-D-5PS-1 El 1-RHRH-311 AUG 2 El 1 OWN PRE C -C HI 1 El 1 -2RHR-20A-D-BPS 8-35 IS1 C3.20 1 El 1 -2RHR-20A-D-BPS El 1-RHRH-310 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-20A-D-9PL-1 THRU 4 8-35 IS1 C3.20 1 El 1 -2RHR-20A-D-9PL-1 THRU 4 El 1-RHRH-22 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-20A-PD-A-6PS 8-43 IS1 C3.20 1 El 1 -2RHR-20A-PD-A-6PS El 1-RHRH-37 AUG 2 El 1 OWN PRE Page 4 - 23 111 812006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Third 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 C -C HI 1 El 1-2RHR-20A-PD-C-15PS-1 AND 2 8-45 IS1 C3.20 1 El 1 -2RHR-20A-PD-C-15PS-1 AND 2 El 1-RHRH-38 AUG 2 El I OWN PRE C -C HI 1 El 1-2RHR-20A-PD-C-8PS-3 AND 4 5-45 IS1 C3.20 1 El I -2RHR-20A-PD-C-8PS-3 AND 4 El 1-RHRH-40 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-20B-D-1 PS-3 AND 4 8-47 IS1 C3.20 I El 1-2RHR-20B-D-1 PS-3 AND 4 El l-RHRH-200 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-20B-0-1 PS-5 8-41 IS1 C3.20 1 El 1 -2RHR-20B-D-1 PS-5 El 1-RHRH-17 AUG 2 El I OWN PRE C-C HI 1E11-2RHR-205-D-5PS ISIIl 5-41 IS1 C3.20 1 El 1 -2RHR-20B-D-5PS El 1-RHRH-194 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-20B-D-8PS 8-41 IS1 C3.20 1 El 1 -2RHR-20B-D-8PS El 1-RHRH-193 AUG 2 El 1 OWN PRE C -C H1 1 El 1 -2RHR-206-D-9PL-1 THRU 4 8-41 IS1 C3.20 1 El 1-2RHR-20B-D-9PL-1 THRU 4 El 1-RHRH-16 AUG 2 El I OWN PRE C -C HI 1 El 1-2RHR-205-PD-6-7PS 6-54 IS1 C3.20 1 El 1 -2RHR-205-PD-5-7PS El 1-RHRH-28 AUG 2 El 1 OWN PRE C -C HI 1 El l-2RHR-20B-PD-D-4PL-1 AND 2 8-53 IS1 C3.20 1 El 1 -2RHR-20B-PD-D-4PL-1 AND 2 El 1 -RHRH-209 AUG 2 El I OWN PRE C-C HI 1 El l-2RHR-20B-PD-D-4PS-1 AND 2 8-53 IS1 C3.20 1 El 1 -2RHR-20B-PD-D-4PS-1 AND 2 El 1-RHRH-31 AUG 2 El 1 OWN PRE Page 5 - 23 111 812006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 6 - 23 111 812006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc.

Scope 1 Method I Procedure Code Case Class Summary I ComplD I System C -C HI 1 El 1-2RHR-20C-D-2PS 8-37 IS1 C3.20 1 El 1 -2RHR-20C-D-2PS El 1-RHRH-316 AUG 2 El 1 om PRE C -C HI 1 El 1-2RHR-20C-D-5PL-1 THRU 4 8-37 IS1 C3.20 1 El I-2RHR-20C-D-5PL-1 THRU 4 El 1-RHRH-23 AUG 2 El I om PRE CC H1 1 El 1-2RHR-20C-D-5PS-1 AND 2 8-37 IS1 C3.20 1 El 1 -2RHR-20C-D-5PS-1 AND 2 El 1-RHRH-315 AUG 2 El 1 om PRE C -C HI 1 El 1-2RHR-20C-D-9PL-1 THRU 8 8-37 IS1 C3.20 1 El 1 -2RHR-20C-D-9PL-1 THRU 8 El 1-RHRH-719 AUG 2 El I OWN PRE C-C HI 1 El 1-2RHR-20D-D-2PS 8-40 IS1 C3.20 1 El 1 -2RHR-20D-D-2PS El 1 -RHRH-199 AUG 2 El 1 om PRE C -C HI 1 El 1-2RHR-20D-D-5PL-1 THRU 4 8-40 IS1 C3.20 1 El 1 -2RHR-20D-D-5PL-1 THRU 4 El 1-RHRH-I 3 AUG 2 El 1 om PRE C-C HI 1El1-2RHR-20D-D-5PL-5 AND 6 8-40 IS1 C3.20 1 El 1-2RHR-20D-D-5PL-5 AND 6 El 1-RHRH-198 AUG 2 El 1 ow PRE C -C HI I El 1-2RHR-20-RS-13PS-1 8-33 IS1 C3.20 1 El 1 -2RHR-20-RS-13PS-1 El 1-RHRH-25 AUG 2 El I OWN PRE C -C HI 1 El 1-2RHR-20-RS-17PS-1 8-33 IS1 C3.20 1 El 1 -2RHR-20-RS-17PS-1 El 1-RHRH-24 AUG 2 El I OWN PRE C -C H1 1 El 1-2RHR-20-RS-5PS-1 AND 2 8-33 IS1 C3.20 I El 1 -2RHR-20-RS-5PS-1 AND 2 El 1-RHRH-203 AUG 2 El 1 OWN PRE N m C) 2 2 I F I F ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - - - - - - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - - - - - - - - - ---- - - - - - - - - - - - - ---- - - - - - - - - - - - -

Revision:

I HNP-1 Third Interval Class 2 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 C -C HI 1 El 1-2RHR-20-RS-5PS-3 6-33 IS1 C3.20 1 El 1 -2RHR-20-RS-5PS-3 Ell-RHRH-26 AUG 2 El I OWN PRE C -C H1 1 El 1-2RHR-20-RS-9PS 6-33 IS1 C3.20 1 El 1-2RHR-20-RS-9PS El 1 -RHRH-202 AUG 2 El 1 OWN PRE C -C HI 1E11-2RHR-24A-HXI-3PS 6-44 IS1 C3.20 1 El 1 -2RHR-24A-HXI-3PS Ell-RHRH-41 AUG 2 El I OWN PRE C -C HI 1Ell-2RHR-24A-R-5PL-1 THRU 4 8-50 IS1 C3.20 1 El I -2RHR-24A-R-5PL-1 THRU 4 El 1 -RHRH-136 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-24A-R-7PS-1 AND 2 8-50 IS1 C3.20 1 El 1-2RHR-24A-R-7PS-1 AND 2 Ell-RHRH-319 AUG 2 El I OWN PRE C -C HI 1 El 1-2RHR-24A-TS-A-10 8-36 IS1 C3.20 1 El 1 -2RHR-24A-TS-A-10 PIPE TO PENETRATION AUG 2 El 1 OWN PRE C -C HI 1El1-2RHR-24A-TS-A-10PL-3 AND 4 8-36 IS1 C3.20 1 El 1 -2RHR-24A-TS-A-1 OPL-3 AND 4 El 1-RHRH-712 AUG 2 El 1 OWN PRE C -C H1 1El1-2RHR-24A-TS-A-3PS-1 6-36 IS1 C3.20 1 El 1 -2RHR-24A-TS-A-3PS-1 El 1-RHRH-4 AUG 2 El 1 OWN PRE C-C HI 1E11-2RHR-24A-TS-A-4PL-1 AND 2 6-36 IS1 C3.20 1 El 1 -2RHR-24A-TS-A-4PL-1 AND 2 El 1-RHRH-709 AUG 2 El 1 OWN PRE C -C HI 1El1-2RHR-24A-TS-A-6PL-1 AND 2 6-36 IS1 C3.20 1 El 1 -2RHR-24A-TS-A-6PL-1 AND 2 El 1-RHRH-711 AUG 2 El 1 OWN PRE Page 7 - 23 111 812006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 8 - 23 111812006 ( Period 1 Period 2 Period 3 o h 2 2 I I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - d V, 2 2 5 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Code Case Class Summary I ComplD I System Scope I Method I Procedure C -C HI 1Ell-2RHR-24A-TS-A-7PL-1 AND 2 8-36 IS1 C3.20 1 El 1 -2RHR-24A-TS-A-7PL-1 AND 2 El 1-RHRH-710 AUG 2 El 1 OWN PRE C -C HI 1 El 1 -2RHR-24A-TS-A-9PL-I THRU 8 8-36 IS1 C3.20 1 El 1 -2RHR-24A-TS-A-9PL-1 THRU 8 El 1-RHRH-323 AUG 2 El I OWN PRE C -C Hl 1 El 1-2RHR-24A-TS-C-13 8-38 IS1 C3.20 1 El 1 -2RHR-24A-TS-C-13 PIPE TO PENETRATION AUG 2 El 1 OWN PRE C-C HI 1 El 1-2RHR-24A-TS-C-16PS 8-38 IS1 C3.20 1 El 1 -2RHR-24A-TS-C-16PS El 1-RHRH-331 AUG 2 El I OWN PRE C -C HI 1 El 1-2RHR-24A-TS-C-5PL-1 AND 2 8-38 IS1 C3.20 1 El 1 -2RHR-24A-TS-C-5PL-1 AND 2 El 1-RHRH-718 AUG 2 El 1 OWN PRE C -C HI 1 El 1 -2RHR-24A-TS-C-9PS 8-38 IS1 C3.20 1 El 1 -2RHR-24A-TS-C-9PS El 1-RHRH-11 AUG 2 El 1 OWN PRE C -C HI 1E11-2RHR-248-BP-12PS 8-56 IS1 C3.20 1 El 1 -2RHR-248-BP-12PS El 1-RHRH-304 AUG 2 El 1 OWN PRE C -C HI 1Ell-2RHR-248-BP-3PL-1 AND 2 8-56 IS1 C3.20 1 El 1-2RHR-248-BP-3PL-1 AND 2 El 1-RHRH-216 AUG 2 El 1 OWN PRE C -C HI 1El1-2RHR-248-BP-8PL-1 THR 8 8-56 IS1 C3.20 1 El 1 -2RHR-248-BP-8PL-1 THR 8 El 1-RHRH-306 AUG 2 El 1 OWN PRE C -C H1 1 El 1-2RHR-24B-BP-8PL-1 THRU 8 B-56 IS1 C3.20 1 El 1 -2RHR-248-BP-8PL-1 THRU 8 El 1-RHRH-306 AUG 2 El 1 om PRE N m C) 2 2 I I .7 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - . - - -

Revision:

1 HNP-1 Third Interval Class 2 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 C-C HI 1 El 1 -2RHR-24B-BP-8PS-9 8-56 IS1 C3.20 1 El 1 -2RHR-24B-BP-8PS-9 El 1-RHRH-305 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-24B-HXI-2PS-1 THRU 4 8-55 IS1 C3.20 1 El 1 -2RHR-24B-HXI-2PS-1 THRU 4 El 1-RHRH-800 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-24B-HXI-3PS 8-55 IS1 C3.20 1 El 1-2RHR-24B-HXI-3PS El 1-RHRH-32 AUG 2 El 1 OWN PRE C-C HI 1Ell-2RHR-24B-R-4PL-1 THRU 4 8-59 IS1 C3.20 1 El 1 -2RHR-24B-R-4PL-1 THRU 4 El 1-RHRH-140 AUG 2 El 1 OWN PRE C-C HI 1 El 1-2RHR-24B-TS-B-10 8-42 IS1 C3.20 1 El 1-2RHR-24B-TS-B-10 PIPE TO PENETRATION AUG 2 El 1 OWN PRE C-C HI 1Ell-2RHR-24B-TS-B-10PL-1 THRU 4 8-42 IS1 C3.20 1 El 1 -2RHR-248-TS-B-1 OPL-1 THRU 4 El 1-RHRH-715 AUG 2 El 1 OWN PRE C-C HI 1 El 1-2RHR-24B-TS-B-3PS-1 8-42 IS1 C3.20 1 El 1 -2RHR-24B-TS-B-3PS-1 El 1-RHRH-1 AUG 2 El 1 OWN PRE C-C H1 1 El 1 -2RHR-24B-TS-B-4PL-1 AND 2 6-42 IS1 C3.20 1 El 1 -2RHR-248-TS-B-4PL-1 AND 2 El 1-RHRH-713 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-24B-TS-B-6PL-1 AND 2 8-42 IS1 C3.20 1 El 1 -2RHR-248-TS-B-6PL-1 AND 2 El 1-RHRH-716 AUG 2 El 1 OWN PRE C-C HI 1 El 1-2RHR-24B-TS-B-8PL-1 AND 2 8-42 IS1 C3.20 1 El 1 -2RHR-248-TS-B-8PL-1 AND 2 El 1-RHRH-714 AUG 2 El 1 OWN PRE Page 9 - 23 111 812006 ( Period 1 Period 2 Period 3 Revision:

1 HNP-1 Third 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 C -C HI 1 El 1-2RHR-240-TS-0-9PL-1 THRU 8 C3.20 1 El 1 -2RHR-240-TS-8-9PL-1 THRU 8 2 El 1 IS1 AUG OWN PRE C -C H1 1 El 1-2RHR-240-TS-D-12 8-39 IS1 PIPE TO PENETRATION AUG OWN PRE C-C HI 1El1-2RHR-248-TS-D-12PL-1 AND 2 8-39 IS1 C3.20 1 El 1 -2RHR-248-TS-D-12PL-1 AND 2 2 El 1 AUG OWN PRE C-C HI 1 El 1-2RHR-240-TS-D-15PS 0-39 IS1 C3.20 1 El 1 -2RHR-240-TS-D-15PS El 1-RHRH-330 AUG 2 El 1 OWN PRE C -C H1 1 El 1-2RHR-248-TS-D-5PL-1 AND 2 8-39 IS1 C3.20 1 El 1-2RHR-240-TS-D-5PL-1 AND 2 El 1-RHRH-720 AUG 2 El 1 OWN PRE C-C HI 1 El 1-2RHR-248-TS-D-9PS 8-39 IS1 C3.20 1 El 1 -2RHR-248-TS-D-9PS El 1-RHRH-8 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-GA-RVD-11 PL-1 THRU 8 8-69 IS1 C3.20 1 El 1 -2RHR-GA-RVD-11 PL-1 THRU 8 El 1-HPSEH-85 AUG 2 El 1 OWN PRE C-C HI 1 El 1-2RHR-GA-RVD-1 PL-1 THRU 8 8-69 IS1 C3.20 1 El 1 -2RHR-GA-RVD-1 PL-1 THRU 8 E41-HPSEH-81 AUG 2 El 1 OWN PRE C -C HI 1 El 1-2RHR-GA-SS-12PS-1 8-67 ISI C3.20 I El 1 -2RHR-GA-SS-12PS-1 E41-HPSEH-68 AUG 2 El I OWN PRE Page 10 - 23 Period 1 Period 2 111812006 I Period 3 Revision:

1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 1 1 - 23 111 812006 1 Period 1 Period 2 Period 3 W h 2 2 I 7 I T- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - S--- - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - . . . - - - - - - - - - - - - - W tn a" 2 I I ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - . - ------------ . - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - . - - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - . ------.----- - . - . - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Scope I Method I Procedure Class Summary I CornplD I System Code Case C -C HI 1 El 1-ZRHR-6A-SS-1 PS-2 8-67 IS1 C3.20 1 El 1 -2RHR-6A-SS-1 PS-2 E41 -HPSEH-37 AUG 2 El 1 om PRE C -C HI 1 El 1-2RHR-6B-RVD-14PL-9 AND 10 5-73 IS1 C3.20 1 El 1-2RHR-6B-RVD-14PL-9 AND 10 E41 -HPSEH-75 AUG 2 El 1 om PRE C -C H1 1 El 1-2RHR-6B-RVD-14PS-1 AND 2 8-73 IS1 C3.20 1 El 1 -2RHR-6B-RVD-14PS-1 AND 2 E41 -HPSEH-75 AUG 2 El 1 om PRE C -C HI 1 El 1-2RHR-6B-RVD-4PS 8-73 IS1 C3.20 1 El 1 -2RHR-6B-RVD-4PS E41 -HPSEH-48 AUG 2 El 1 om pRE C -C H1 1 El 1-2RHR-6B-TSP-3PL-1 AND 2 8-65 IS1 C3.20 1 El 1 -2RHR-6B-TSP-3PL-1 AND 2 El 1-RHRH-74 AUG 2 El 1 OWN PRE C -C H1 1 El 1-2RHR-6B-TSP-5PS-1 AND 2 B-65 IS1 C3.20 1 El 1 -2RHR-6B-TSP-5PS-1 AND 2 El 1-RHRH-76 AUG 2 El 1 om pRE C -C HI 1 El 1-2RHR-8-FPS-11 PS-1 AND 2 8-72 IS1 C3.20 1 El 1 -2RHR-8-FPS-11 PS-1 AND 2 El 1-RHRH-318 AUG 2 El 1 om PRE C-C HI 1 El 1-2RHR-8-FPS-13PS-1 AND 2 8-72 IS1 C3.20 1 El 1-2RHR-8-FPS-13PS-1 AND 2 El 1-RHRH-154 AUG 2 El 1 OWN PRE C -C H1 1 El 1-2RHR-8-FPS-18PS B-72 IS1 C3.20 1 El 1 -2RHR-8-FPS-l8PS El 1-RHRH-207 AUG 2 El 1 om PRE C -C HI 1 El 1 -2RHR-8-FPS-20PL-1 THRU 4 8-72 IS1 C3.20 1 El 1 -2RHR-8-FPS-20PL-1 THRU 4 El 1-RHRH-153 AUG 2 El 1 OWN PRE 9 (Y P) a" 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - -

Revision:

1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 12 - 23 Period 1 Period 2 812006 1 Period 3 0 r- 2 2 I I - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - d Y) 2 2 x I --------..-- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ----S------* - - - - - - - - - - - - ------------ - - - - . - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - . - - ------------ - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Scope I Method I Procedure Code Case Class Summary I ComplD I System C -C HI 1 El 1-2RHR-8-HS-7PS-1 6-70 IS1 C3.20 I El 1 -2RHR-8-HS-7PS-1 El 1-RHRH-243 AUG 2 El I OWN PRE C -C HI 1 E21-2CS-1 OA-TL-1 PL-1 THRU 4 8-51 IS1 C3.20 1 E21-2CS-1 OA-TL-1 PL-1 THRU 4 E21 -CSH-22 AUG 2 E21 om PRE C -C HI 1 E21-2CS-1 OA-TL-7PS 6-5 IS1 C3.20 1 E21-2CS-1 OA-TL-7PS E21 -CSH-23 AUG 2 E21 om PRE C -C HI 1 E21-2CS-1 OB-TL-9PS-1 8-8 IS1 C3.20 1 E21-2CS-1 OB-TL-9PS-1 E21-CSH-28 AUG 2 E21 OWN PRE C-C H1 1 E21-2CS-12A-22PS-1 THRU 4 6-6 IS1 C3.20 1 E21-2CS-12A-22PS-1 THRU 4 E21-CSH-75 AUG 2 E21 OWN pRE C -C HI 1 E21-2CS-12A-24PS-1 AND 2 B-6 IS1 C3.20 1 E21-2CS-12A-24PS-1 AND 2 E21-CSH-35 AUG 2 E21 om PRE C -C HI 1 E21-2CS-12A-27PS-1 THRU 4 6-6 IS1 C3.20 1 E21-2CS-12A-27PS-1 THRU 4 E21 -CSH-76 AUG 2 E21 OWN PRE C-C HI 1 E21-2CS-12A-34PS-1 AND 2 6-6 IS1 C3.20 1 E21-2CS-12A-34PS-1 AND 2 E21 -CSH-77 AUG 2 E2 1 om PRE C -C H1 1 E21-2CS-12A-36PS 6-6 IS1 C3.20 1 E21-2CS-12A-36PS E21 -CSH-79 AIJG 2 E21 OWN PRE C -C HI 1 E21-2CS-12A-7PL-1 THRU 4 B -3 IS1 C3.20 1 E21-2CS-12A-7PL-1 THRU 4 E21 -CSH-21 AUG 2 E21 OWN PRE 4 N rn g 7 F - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . . - - - - - - - - - - - - - - - - . - - - - - - - -

Revision:

1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 13 - 23 Period 1 Period 2 111812006 I Period 3 (P I- 2 2 I I - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - d V) 2 2 z 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - - S----------- - - - - - - - - - - - - -----------. - - - - - - - - - - - - ------------ - - - - - - - - - - - - -------.---- - - - - - - - . - - - - ------------ - - - - - - - - - - - - -----------. - - - - - - . - . - - - ---.-------- - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Code Case Class Summary I ComplD I System Scope I Method I Procedure C -C H1 1 E21-2CS-12A-8PS-1 AND 2 8-3 IS1 C3.20 1 E21-2CS-12A-8PS-1 AND 2 E21-CSH-71 AUG 2 E21 om PRE C -C HI 1 E21-2CS-12A-9PS-1 THRU 4 8-3 IS1 C3.20 1 E21-2CS-12A-9PS-1 THRU 4 E21 -CSH-72 AUG 2 E21 0I"hpJ PRE C-C HI 1 E21-2CS-128-10PL-1 THRU 4 ISllMTINMP-ES-024-401 8-7 IS1 C3.20 1 E21-2CS-128-1 OPL-1 THRU 4 E21-CSH-26 AUG 2 E21 OWN PRE C -C Hl 1E21-2CS-126-11 PS-1 AND 2 ISIIMTINMP-ES-024-401 6-7 IS1 C3.20 1 E21-2CS-126-11 PS-1 AND 2 E21 -CSH-57 AUG 2 E21 om PRE C-C HI 1E21-2CS-126-12PL-1 THRU 8 6-7 IS1 C3.20 1 E21-2CS-128-12PL-1 THRU 8 E21-CSH-58 AUG 2 E21 OWN PRE C -C HI 1 E21-2CS-126-15 6-7 IS1 C3.20 1 E21-2CS-128-15 PIPE TO PENETRATION AUG 2 E21 om PRE C-C HI 1 E21-2CS-126-17PS-1 THRU 3 8-7 IS1 C3.20 1 E21-2CS-128-17PS-1 THRU 3 E21-CSH-60 AUG 2 E21 om PRE C -C H1 1E21-2CS-128-27PL-1 THRU 4 6-9 IS1 C3.20 1 E21-2CS-126-27PL-1 THRU 4 E21 -CSH-30 AUG 2 E21 OWN PRE C -C H1 1 E21-2CS-16A-TS-1 I PS-3 8-2 IS1 C3.20 1 E21-2CS-16A-TS-11 PS-3 E21-CSH-19 AUG 2 E21 OWN PRE C -C H1 1E21-2CS-16A-TS-16PS 8-2 IS1 C3.20 1 E21-2CS-16A-TS-16PS E21 -CSH-42 AUG 2 E21 OWN PRE N rn C? 2 2 I I .7 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - . - - - - - - - - -

Revision:

1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I CornplD I System Scope I Method I Procedure Code Case C -C HI 1 E21-2CS-16A-TS-17PS 6-2 IS1 C3.20 1 E21-2CS-16A-TS-17PS E21 -CSH-20 AUG 2 E2 1 OWN PRE C -C HI 1 E21-2CS-16A-TS-7PS-1 6-2 IS1 C3.20 1 E21-2CS-16A-TS-7PS-1 E21-CSH-18 AUG 2 *21 OWN PRE C -C HI 1 E21-2CS-16B-TS-1OPS ISllMTlNMP-ES-024-401 B-1 IS1 C3.20 1 E21-2CS-166-TS-10PS E21 -CSH-10 AUG 2 *21 OWN PRE C-C HI 1 E21-2CS-166-TS-11 B-1 IS1 C3.20 1 E21-2CS-16B-TS-11 PIPE TO PENETRATION AUG 2 E21 OWN PRE C -C HI 1 E21-2CS-166-TS-15PS 6-1 IS1 C3.20 1 E21-2CS-16B-TS-15PS E21 -CSH-41 AUG 2 E21 OWN PRE C -C HI 1 E21-2CS-166-TS-16PS B-1 IS1 C3.20 1 E21-2CS-166-TS-16PS E21-CSH-11 AUG 2 E21 OWN PRE C -C HI 1 E21-2CS-16B-TS-7PS B-1 IS1 C3.20 1 E21-2CS-16B-TS-7PS E21-CSH-9 AUG 2 E21 OWN PRE C -C H1 1 E41-2HPCI-10-SS-11 PL-I THRU 8 8-22 IS1 C3.20 1 E41-2HPCI-10-SS-11PL-1 THRU 8 E41-HPSEH-61 AUG 2 E4 1 OWN PRE C -C HI 1 E41-2HPCI-10-SS-11 PL-9 6-22 ISI C3.20 1 E41-2HPCI-10-SS-1 1 PL-9 E41-HPSEH-20 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-10-SS-17PS-I 8-1 8 IS1 C3.20 1 E41-2HPCI-10-SS-17PS-1 E41 -HPSEH-29 AUG 2 E41 OWN PRE Page 14 - 23 Period 1 Period 2 111812006 1 Period 3 Revision:

1 HNP-1 Third Interval Class 2 IS1 Plan Southern Nuclear Operating Company Page 15 - 23 111812006 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 H1 1 E41-2HPCI-10-SS-I PL-1 THRU 4 8-2 1 IS1 C3 20 1 E41-2HPCI-10-SS-1 PL-1 THRU 4 E41-HPSEH-813 AUG 2 E41 om PRE CC HI 1 E41-2HPCI-10-SS-20 8-1 8 IS1 C3.20 1 E41-2HPCI-10-SS-20 PIPE TO PENETRATION AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-10-SS-20PS-1 AND 2 B-18 IS1 C3.20 1 E41-2HPCI-10-SS-20PS-1 AND 2 E41 -HPSEH-30 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-10-SS-21 PL-3 THRU 10 B-19 IS1 C3.20 1 E41-2HPCI-10-SS-21 PL-3 THRU 10 E41 -HPSEH-60 AUG 2 E41 OWN PRE Ct HI 1 E41-2HPCI-10-SS-21 PS-1 AND 2 B-19 IS1 C3.20 1 E41-2HPCI-10-SS-21 PS-1 AND 2 E41-HPSEH-31 AUG 2 E41 om PRE C-C HI 1 E41-2HPCI-10-SS-21 PS-11 B-19 IS1 '23.20 1 E41-2HPCI-10-SS-21 PS-1 1 E41-HPSEH-32 AUG 2 E41 om PRE C -C HI 1 E41-7HPCI-10-SS-27PL-1 THRU 8 B-19 IS1 C3.20 1 E41-2HPCI-10-SS-27PL-1 THRU 8 E41-HPSEH-56 AUG 2 E41 OWN PRE C-C HI 1 E41-2HPCI-10-SS-32PL-1 DEVICE 8-20 IS1 C3.20 1 E41-2HPCI-10-SS-32PL-1 DEVICE E41 -HPSEH-54 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-10-SS-32PS-1 8-20 IS1 C3.20 1 E41-2HPCI-10-SS-32PS-1 E41 -HPSEH-55 AUG 2 E41 om PRE C -C HI 1 E41-2HPCI-10-SS-3PL-1 THRU 4 8-27 IS1 C3.20 1 E41-2HPCI-10-SS-3PL-I THRU 4 El 1 -RBHX-83 AUG 2 E41 OWN PRE 9 N P) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - W V) 2 2 5 5 ------------ - - - - - - . - - - . - ------------ - - - - - - - - - - - - ---------.-- - - - - . - - - - - - - -.---------- - - - - - - - - - - - - ------------ - - - - - - . - - - - - ------------ - - - - - - - - - - - - ------.----- - - - - - - - - - - - - ------.----- - - - - - - - - - - - - ------------ - - - . - - . - - - - - ---.---.---- - - - - - - - - . - - - Wh 2 2 I I r - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - . - - - - - . . . - . - - - - - - - - - - - - - - - - - - - - - - .

Revision:

1 HNP-1 Third 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 C-C HI 1E41-2HPCI-14-R-21 PS-1 AND 2 B-11 IS1 C3.20 1 E41-2HPCI-14-R-21 PS-1 AND 2 E41 -HPCIH-23 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-14-R-22 B-1 1 IS1 C3.20 1 E41-2HPCI-14-R-22 PENETRATION TO PIPE AUG 2 E41 OWN PRE C-C HI 1 E41-2HPCI-14-R-28PS-1 AND 2 B-I I IS1 C3.20 1 E41-2HPCI-14-R-28PS-1 AND 2 E41-HPCIH-38 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-14-R-32PS B-11 IS1 C3.20 1 E41-2HPCI-14-R-32PS E41-HPCIH-27A AUG 2 E41 OWN PRE C -C HI 1E41-2HPCI-14-R-34PL-1 THRU 4 B-11 IS1 C3.20 1 E41-2HPCI-14-R-34PL-1 THRU 4 E41-HPCIH-28 AUG 2 E41 OWN PRE C-C HI 1 E41-2HPCI-14-R-6PS ISllMTl 0-1 0 IS1 C3.20 1 E41-2HPCI-14-R-6PS E41-HPCI-11B AUG 2 E41 OWN PRE C-C HI 1 E41-2HPCI-14-R-9PL-1 THRU 8 lSllMT1 B-10 IS1 C3.20 1 E41-2HPCI-14-R-9PL-1 THRU 8 E41-HPCIH-12 AUG 2 E41 OWN PRE C -C HI 1E41-2HPCI-16-CS-11 PS-I 8-1 3A IS1 C3.20 1 E41-2HPCI-16-CS-11 PS-1 E41-HPCI-H7 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-16-CS-PS-1 B-13A IS1 C3.20 1 E41-2HPCI-16-CS-PS-1 E41-HPCI-H1 AUG 2 E41 OWN PRE C -C Hl 1 E41-2HPCI-16-PS-1 PS 8-87 IS1 C3.20 1 E41-2HPCI-16-PS-I PS E41-HPCIH-9 AUG 2 E41 OWN PRE Page 16 - 23 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Third Interval Class 2 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 C -C HI 1 E41-2HPCI-16-RD-1 PL-1 THRU 8 ISIIMTI 8-1 7 IS1 C3.20 1 E41-2HPCI-16-RD-1 PL-1 THRU 8 E41 -HPSEH-89 AUG 2 E41 OWN PRE C-C HI IE41-2HPCI-16-TS-I I PS-I 6-1 3 IS1 C3.20 1 E41-2HPCI-16-TS-1 1 PS-1 E41 -HPCIH-8 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-16-TS-4PS-1 8-1 3 IS1 C3.20 1 E41-2HPCI-16-TS-4PS-1 E41-HPCIH-11 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-16-TS-7PL-1 THRU 8 8-1 3 IS1 C3.20 1 E41-2HPCI-16-TS-7PL-1 THRU 8 E41 -HPCIH-700 AUG 2 E41 OWN PRE C -C HI 1 E41-2HPCI-16-TS-7PS-1 THRU 4 8-1 3 IS1 C3.20 1 E41-2HPCI-16-TS-7PS-1 THRU 4 E41-HPCIH-10 AUG 2 E41 0 WN PRE C -C HI 1 E41-2HPCI-18-TD-5PS-1-1 AND 2 ISIIMTI 8-1 4 IS1 C3.20 1 E41-2HPCI-18-TD-5PS-1-1 AND 2 E41-HPSEH-1 AUG 2 E4 1 0 WN PRE C -C HI 1 E41-2HPCI-18-TD-5PS-2-1 AND 2 8-1 4 IS1 C3.20 1 E41-2HPCI-18-TD-5PS-2-1 AND 2 E41 -HPSEH-2 AUG 2 E41 OWN PRE C -C H1 1 E41-2HPCI-18-TD-6PL-1 THRU 4 8-1 4 IS1 C3.20 1 E41-2HPCI-18-TD-6PL-1 THRU 4 E41-HPSEH-701 AUG 2 E41 OWN PRE C -C HI 1E41-2HPCI-20-TD-11 PS-1 8-1 5 IS1 C3.20 1 E41-2HPCI-20-TD-11 PS-1 E41 -HPSEH-10 AUG 2 E4 1 OWN PRE C -C HI 1E41-2HPCI-20-TD-4PL-1 THRU 8 8-1 5 IS1 C3.20 1 E41-2HPCI-20-TD-4PL-1 THRU 8 *41-HPSEH-6 AUG 2 E41 OWN PRE Page 17- 23 Period 1 Period 2 111812006 1 Period 3

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 1 Basis Doc-Class 3.doc Page 1 of 7 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-1 Boundary Diagrams listed below:

HB-11001 Plant Service Water HB-11024 Plant Service Water HB-11600 Plant Service Water HB-11609 Plant Service Water HB-11601 Plant Service Water HB-11631 Plant Service Water HB-11638 Plant Service Water HB-16011 Plant Service Water (Class 3 portion)) HB-11004 RHR Service Water HB-16016 Condensate Transfer (HPCI and RCIC Pump Suction) HB-16062 Main Steam Relief Valve Lines HB-16002 Fuel Pool Cooling

Per HB-16002, the piping from RHR to the Spent Fuel Pool is Class 0 after the spectacle flanges. However, cooling water must be supplied to the pool.

Therefore, per HB-16002 (Note 5) there is an NRC commitment to ma intain a certain portion of fuel pool cooling piping as Class 3. Per HB-16011 this is the piping that functions as the fuel pool makeup source from the Plant Service Water system. It includes the piping from between 1P41-F070A and 1P41-F070B through valve 1P41-F103 to the makeup diffuser in the spent fuel pool.

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.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 1 Basis Doc-Class 3.doc Page 2 of 7 Rev. 1 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.

Plant Service Water (PSW) Evaluation Equipment required to be cooled during emergency conditions by PSW includes:

1. HB-11001 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. The Class 3 piping is in the examination scope for welded attachments except for 4" and under piping. PSW pump 1P41-C001C and 1P41-C001A with the associated non-exempt lines are shown on Isometric Sketches C-8 and C-11. PSW pump 1P41-C001B and 1P41-C001D with the associated non-exempt lines are shown on Isometric Sk etches C-10 and C-9 (including the 30" Dilution Line to the end of scope at the anchor past 1P41-F312). Figure C-8A provides details for the strainers.

2. HB-11004 shows Pump Motor Cooling water from PSW (See HB-11001 above).

These lines are under 4" in size; therefore, there are no PSW welded attachment examination scope on this drawing. Therefore, welded attachments shown on C-12, C-13, C-14, C-15, C-16 are exempt

3. HB-11024 shows the Division 1 and Division II Reactor Building PSW Supply splitting off from the 30" Supply Line to th e Turbine Building (from HB-11600). It is underground piping (shown on drawing H-11139) and not included in the scope of welded attachment examinations until it enters the Reactor Building (See HB-16011). There are no associated isomet ric sketches for this drawing.

4. HB-16011 shows the 8" Division I and 6" Division II Reactor Building Service Water System. The Division I and II lines are discussed below for inclusion in the examination scope.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 1 Basis Doc-Class 3.doc Page 3 of 7 Rev. 1 Isometric sketch C-36 shows the 8" piping where it enters the Reactor Building at valve 1P41-F067. The welded attachments on these sketches are in the examination scope because these lines provide required cooling water to Emergency Makeup Water to the Fuel Pool, RHR & Core Spray Pump Room

Coolers, and RCIC Pump Room Coolers and the pressure temperature exemption cannot be used. (Division I)

There is a 6" line from C-36 to C-37, C-37A, and C-38 which provides Emergency Makeup Water to the Fuel Pool.

Therefore, the pressure/temperature exemption cannot be used on these lines. There is a portion of 6" piping from C-22 to valve 1P41-F-052A on C-36 that provides a normally locked crosstie between the two divisions. This piping is the examination scope.

There is also an 8" line to C-39 de scribed below. (Division I)

The 8" piping on C-39 provides a header for small diameter RHR & Core Spray Pump Room Coolers which are exempt on size. Therefore, the pressure/temperature exemption cannot be used on these lines; however, the small diameter RHR & Core Spray Pump Room Cooler lines are exempt (C-40 and C-41). (Division I)

C-39 transitions into C-73 which like C-39 provides cooling water to the small diameter RCIC Pump Room Coolers and Reactor Recirc Pump MG Set Coolers. Therefore, the pressure/temperature exemption cannot be used on these lines; however, the small diameter RCIC Pump Room Cooler lines are exempt. Cooling is maintained through the small diameter Reactor Recirc Pump MG Set Coolers but is not required per Page 10.7-7 of the FSAR. C-73 terminates at Containment Isolation valve 1P41-F049 where the system becomes Class 2 inside containment (see Class 2 dr awing B-104). (Division I)

Isometric sketch C-21 shows the 6" piping where it enters the Reactor Building at valve 1P41-F066. C-21 transitions into C-22 and the welded attachments on these sketches are in the examination scope until the 6" X 4" reducer on C-22 where they become exempt on size.

RHR Pump Seal Coolers , RHR/Core Spray Pump Room Coolers , and HPCI Pump Room Coolers are thus exempt on size; therefore, welded attachments shown on C-23, C-24 and C-25 are exempt.

(Division II)

There is a portion of 6" piping from C-22 to valve 1P41-F-052A on C-36 that provides a normally locked crosstie between the two divisions. This piping is the examination scope. (Division II)

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 1 Basis Doc-Class 3.doc Page 4 of 7 Rev. 1 The return lines are discussed below for inclusion in the examination scope.

C-120 begins at the discharge of 1P41-F050 (See Class 2, B-102). The return lines from Division I and II (C-120 and C-121) combine into an 8" header on C-120 and terminates when the class becomes Class 0.

5. All Turbine Building Supply Piping downstream of 1P41-F3 10D (Division II) and 1P41-F310C (Division I) located in outsid e valve boxes is exempt on pressure and temperature because there is not a safety-related cooling unit.

6. The Diesel Generators units are shown on HB-11600. Water to these components are supplied from Division I and II supp lies (originating on HB-11001) and enter from underground piping through the Diesel Generator Building floor on Figure C-19 in two locations. One 8" supply line on Figure C-19 connects to C-17 for the supply piping for DG "1A" and the Unit 1 portion of the supply to DG "1B" which also receives cooling water from Unit 2 (Figure C-37). The other 8" supply line on C-19 goes to C-18 as the DG "1C" supply. Return piping for DG "1A" and DG "1C" are shown on C-20. (The return piping for DG "1B" is on the Unit 2 figures). All welded attachments are in the examination scope except for the small diameter instrument lines, drain lines, etc.

7. The Control Room Air Conditioning units are shown on HB-11609.

All lines are 4";

therefore, all integral attachments on HB-11609 are exempt on size. The 2" supply for the Control Room Air Conditioning originates at Coordinate F-3 on HB-16011 and is exempt on size.

RHR Service Water Evaluation

1. HB-11004 describes the Class 3 intake structure Divi sion I and Division II Supply Piping. This is the source of all safety-relate RHRSW water to the essential components and thus must be included. The Class 3 piping is in the examination scope for welded attachments except for 4" and under piping. RHRSW pump 1E11-C001B and 1E11-C001D with the associated non-exempt lines are shown on Isometric Sketch C-1 and C-2. RHRSW pump 1E11-C001A and 1E11-C001D with the associated non-exempt lines are shown on Isometric Sketch C-3 and C-4. (At this point the piping goes underground)>

2. HB-16329 describes the Division II supply from the underground Reactor Building penetration to RHR Heat Exchanger B on Isometric Sketch C-5 and the return to the Reactor Building penetration on Isometric Sketch C-7. The RHRSW pipe entering and leaving the Reactor building is underground and outside the scope of these examinations.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 1 Basis Doc-Class 3.doc Page 5 of 7 Rev. 1

3. HB-16330 describes the Division I supply from the underground Reactor Building penetration to RHR Heat Exchanger B on Isometric Sketch C-6 and the return to the Reactor Building penetration on Isometric Sketch C-7. The RHRSW pipe entering and leaving the Reactor building is underground and outside the scope of these examinations.

Main Steam Relief Piping Evaluation Isometric Sketches C-78 through C-94 show th e 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 For HNP-1 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.

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 - Pressure Vessels

None Identified.

Item D1.20 - Piping

As shown in Schedule Works, Hatch 1 has 136 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 Code Case N-598.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 1 Basis Doc-Class 3.doc Page 6 of 7 Rev. 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.

Item D1.30 (Pumps) and D1.40 (Valves)

None Identified.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN CLASS 3 COMPONENTS Hatch 1 Basis Doc-Class 3.doc Page 7 of 7 Rev. 1 ISI PLAN TABLES Beginning in 2005, ISI Plan Tables are generated by the industry standard ScheduleWorks ISI software. The following tables were generated 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 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.

Southern Nuclear Operating Company Page 1 - 1/30/2006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS D-A D1.20 136 10% 13.6 14 14 Total: 1 36 14 14 14 ACTUAL ROUND COUNT PERIOD UP 5 66.18% 65% 5 64.20% 65% ACTUAL ROUND COUNT PERIOD UP 4 29.41% 29%

4 28.50% 29%

ACTUAL ROUND COUNT PERIOD UP 5 102.94% 100% 5 100% 100%

Revision:

1 HNP-1 Fourth Interval Class 3 IS1 Plan Page 1 - 14 112512006 1 Southern Nuclear Operating Company 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 4 2 2 ,I 5 D A HI 1821-H812 AT C-79 IS1 Dl .20 1 821 -H812 A7T Lugs AIJG 3 621 ow PRE D -A HI 1821-H814 ATT C-90 IS1 Dl .20 1 821 -Ha14 AT Lugs AUG 3 821 ow PRE D A HI 1821-H816AT C-78 IS1 Dl .20 1 821 -H816 AT Lugs AIJG 3 821 ow PRE D -A HI 1821-H818 AT C-89 IS1 Dl .20 1821 -H818 An Lugs AUG 3 821 ow PRE D A HI 1821-H822 AT C-8 1 IS1 Dl .20 1821 -Ha22 AT Lugs AIJG 3 821 ow PRE D -A HI 1 821-MVVH-3 A7T ISIII C-80 IS1 Dl .20 1821 -MVVH-3 A7T Lugs AIJG 3 821 OWN PRE D -A HI 1821 -MVVH-32 ATT C-91 IS1 DI .20 1821 -MWH-32 AT Lugs AIJG 3 821 ow PRE D A HI 1821-MVVH-33 AT C-91 IS1 Dl .20 1 821 -MVVH-33 AT Lugs AIJG 3 821 ow PRE D -A HI 1 821-MVVH-34 AT C-9 1 IS1 Dl .20 1 821 -MVVH-34 A7T Lugs AIJG 3 821 ow PRE DA HI 1621-MVVH-35 AT C-92 IS1 Dl .20 1 821 -MVVH-35 ATT Lugs AUG 3 821 OWN PRE d V) 2 2 5 5 (D b 2 2 5 5 . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----- - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------.--- - - - - - - - - - - - - ------------ . . - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - . - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - . - - - - ------------ - - - - - - - - . - - - -----------. - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - . - - . - - - - -

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1 HNP-1 Fourth Interval Class 3 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 D -A HI 1 821-MVVH-36 AlT C-92 IS1 Dl .20 1821 -MVVH-36 ATT Lugs AUG 3 82 1 OWN PRE D A Hl 1821-MWH-37AlT C-92 IS1 Dl .20 1821 -MVVH-37 ATT Lugs AUG 3 82 1 OWN PRE D-A HI 1 821-MVVH-701 AlT C-80 IS1 Dl .20 1 821 -MWH-701 AT Lugs AUG 3 821 OWN PRE D-A HI 1 821-MVVH-8 ATT C-85 IS1 Dl .20 1821 -MVVH-8 ATT Lugs AUG 3 821 OWN PRE D-A HI 1821-MVVH-9 AT C-87 IS1 Dl .20 1821 -MVVH-9 AlT Lugs AU G 3 821 OWN PRE D -A H1 1821-R3ATT C-78,-89 IS1 Dl .20 1 B21 -R3 AT Lugs AUG 3 821 OWN PRE D -A HI 1821-R7 ATT C-80 IS1 Dl .20 1 821 -R7 ATT 3 821 Lugs AU G OWN PRE D -A HI 1 821-R8 ATT ISIII C-81 IS1 Dl .20 1 821 -R8 ATT Lugs AUG 3 821 OWN PRE D A Hl 1821-SS-3ATT C-90,-79 IS1 Dl .20 1821 -SS- 3 ATT Lugs AUG 3 821 OWN PRE D -A Hl 1821-SS-4AlT C-79 IS1 Dl 20 1821 -SS- 4 AT Lugs AUG 3 821 OWN PRE Period 1 Period 2 Period 3 Revision:

1 Category, ItemNO, Class Summary I ComplD I System HNP-1 Fourth Interval Class 3 IS1 Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Scope I Method I Procedure Code Case D -A HI 1 821-SS- 5 ATT C-89,-78 IS1 Dl -20 1 821 -SS- 5 ATT Lugs AUG 3 821 OWN PRE D A HI 1 B21 -SS- 9 ATT C-81 IS1 Dl .20 1 821 -SS- 9 ATT Lugs AUG 3 821 OWN PRE D -A H1 1821-SS-10ATT C-81 IS1 Dl .20 1 821 -SS-10 ATT Lugs AUG 3 821 OWN PRE D -A H1 1821 -SS-12 ATT C-80 IS1 Dl .20 1 821 -SS-12 ATT Lugs AUG 3 821 OWN PRE D -A HI 1821 -SS-13 ATT C-80 IS1 Dl .20 1 821 -SS-13 ATT Lugs AUG 3 B21 OWN PRE D -A H1 1821-SS-15 ATT lSl1l C-83 IS1 Dl .20 1821 -SS-15 ATT 3 821 Lugs AUG OWN PRF , ,.- D -A HI 1821 -SS-16 ATT C-83 IS1 Dl .20 1 821 -SS-16 ATT Lugs AUG 3 821 OWN PRE D -A HI 1821 -SS-26 ATT C-85 IS1 Dl .20 1 B21 -SS-26 ATT Lugs AUG 3 821 0 WN PRE D -A HI 1821 -SS-28 ATT C-85 IS1 Dl .20 1 821 -SS-28 ATT Lugs AUG 3 821 OWN PRE D -A H1 1821 -SS-29 ATT C-87 IS1 Lugs AUG 0 WN PRE Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 3 IS1 Plan Southern Nuclear Operating Company Page 4 - 14 112512006 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 D -A HI 1821 -SS-31 AlT C-87 IS1 01 .20 1 821 -SS-31 AT Lugs AUG 3 821 OWN PRE D -A HI 1821-SS-338 AT C-88 IS1 Dl .20 1821 -SS-338 An Lugs AUG 3 821 om PRE D -A HI 1821 -SS-39 All C-79 IS1 Dl .20 1 821 -SS-39 AlT Lugs AUG 3 821 om PRE D A H 1 1 B21 -SS-40 AlT C-90 IS1 Dl .20 1 821 -SS-40 AlT Lugs AUG 3 82 1 OWN PRE D -A HI 1821-SS-45 ATT ISIII C-82 IS1 Dl .20 1821 -SS-45 AlT Lugs AUG 3 821 om PRE D A HI 1B21-SS-H701 AlT C-86 IS1 Dl .20 1821 -SS-H701 All Lugs AUG 3 B21 om PRE D A H1 1821 -SS-H702 All C-88 IS1 Dl .20 1821 -SS-H702 All Lugs AUG 3 821 om PRE D A HI 1821-SS-H703 AlT C-88 IS1 Dl .20 1821 -SS-H703 AlT Lugs AUG 3 B21 OWN PRE D -A H1 1El1-ISH-1 All C-3 IS1 Dl .20 IElI -ISH- I ATT Lugs AUG 3 El 1 OWN pRE D -A HI 1 El 1-ISH- 2 AlT C-3 IS1 Dl .20 1 El 1 -ISH- 2 ATT Lugs AUG 3 El 1 OWN PRE w rn 2 2 5 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -s---------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------...- - - - - - - - - - - - - ------------ - - - - - - . - - - - - ----------.- - - - - - - - - - - - - e, 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - . - . - - - w h 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . . - . . - - - - .

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1 HNP-1 Fourth Interval Class 3 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 D A HI 1E11-RHRH-298 ATT C-7 IS1 Dl .20 1 El 1-RHRH-298 ATT Lugs AUG 3 El 1 OWN PRE D -A HI 1 El 1-RHRH-299 ATT C-7 IS1 Dl .20 1 El 1-RHRH-299 ATT Lugs AUG 3 El 1 OWN PRE D A HI 1El1-RHRH-301 ATT C-7 IS1 Dl .20 1E11-RHRH-301 ATT Lugs AUG 3 El 1 OWN PRE D -A HI 1E11-RHRH-302 ATT C-7 IS1 Dl .20 1 El 1 -RHRH-302 ATT Lugs AUG 3 El I OWN PRE D -A HI 1 El 1-RHRH-303 ATT C-7 IS1 Dl .20 1 El 1 -RHRH-303 ATT LUgS AUG 3 El 1 OWN PRE D -A HI 1E11-RHRH-343 AT C-6 IS1 Dl .20 1 El 1-RHRH-343 ATT Lugs AUG 3 El 1 OWN PRE D -A HI 1El1-RHRH-344 ATT C-6 IS1 Dl .20 1 El 1 -RHRH-344 AT1 Lugs AUG 3 El I OWN PRE D -A H1 1E11-RHRH-345ATT C-6 IS1 Dl .20 1 El 1-RHRH-345 ATT Lugs AUG 3 El 1 OWN PRE D -A HI 1E11-RHRH-410 ATT C-5 IS1 Dl .20 1 El 1-RHRH-410 ATT Lugs AUG 3 El 1 OWN PRE D A HI 1 ESl-2RCIC-6-CST-14PL-1 THRU 8 C-94A IS1 Dl .20 1 E51-2RCIC-6-CST-14PL-I THRU 8 E51-RCIC-H9 AUG 3 E51 OWN PRE Period 1 Period 2 112512006 1 Period 3 0 r- Z 2 c 5 ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- ----

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1 HNP-1 Fourth Interval Class 3 IS1 Plan Southern Nuclear Operating Company Page10- 14 Period 1 Period 2 112512006 I Period 3 w I. 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - S-- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - . - - - - - - - - - - - - - - - - - - . - . - - - - - - - - - - - - - - - - - - - - - - - . - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case D-A H1 1 P41-ISH-48 AlT C-1 I IS1 Dl .20 1 P41-ISH-48 ATT Lugs AUG 3 P41 om PRE D-A HI 1 P41-ISH-49 AlT C-9 IS1 Dl .20 1 P41 -ISH-49 ATT Lugs AUG 3 P41 om pRE D A H1 1 P41 -1SH-67 AlT C-1 0 IS1 Dl .20 1 P41 -ISH-67 ATT Lugs AUG 3 P41 om PRE D-A HI 1 P41-ISH-68 ATT ISlll C-1 0 IS1 Dl .20 I P41-ISH-68 AlT Lugs AUG 3 P41 OWN PRE D -A HI 1 P41 -ISH-69 AlT C-8 IS1 Dl .20 1 P41 -ISH-69 ATT Lugs AUG 3 P41 OWN PRE D A HI 1 P41-ISH-70 Am C-8 IS1 Dl .2O 1 P41 -ISH-70 ATT Lugs AUG 3 P41 om pRE D-A HI 1P41-ISH-71 AlT C-1 0 IS1 Dl .20 1 P41-ISH-71 ATT Lugs AUG 3 P41 om PRE D -A HI 1 P41-SDGH-4 AlT C-18 IS1 Dl .20 1 P41-SDGH-4 AT Lugs AUG 3 P41 om PRE D -A HI 1P41-SDGH-7 AT ISIII C-18 IS1 01 .20 1 P41 -SDGH- 7 AT Lugs AUG 3 P41 OWN PRE D -A HI 1 P41-SDGH-17 ATT C-17 IS1 Dl .20 1 P41 -SDGH-17 ATT Lugs AUG 3 P41 om PRE 4 c.3 ; 2 5 5 - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - d V) 2 g 5 5 ------------ - - - - - - . - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - -------..--- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -----s------ - - . - - - - - - - - - .-.--------- - - - - - - - . . - . -

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

Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case D A H1 1P41-SWH-181 Al-r C-36 IS1 Dl .20 1 P41 -SWH-181 Al-r Lugs AUG 3 P41 OWN PRE D A H1 1 P41 -SWH-184 Al-r C-38 IS1 Dl .20 1 P41 -SWH-184 Al-r Lugs AUG 3 P41 OWN PRE D A H1 1 P41 -SWH-185 AT C-38 IS1 Dl .20 1 P41 -SWH-185 All' 3 P41 Lugs AUG OWN a ,*- D -A HI I P41 -SW-190 Al-r ISlll C-37A IS1 Dl .20 1 P41 -SWH-190 Al-r Lugs AUG 3 P41 OWN PRE D-A HI 1 P41-SWH-191 All' C-37A IS1 Dl .20 1 P41-SWH-191 Al-r Lugs AUG 3 P41 OWN PRE D-A HI 1 P41-SWH-192 All' C-37A IS1 Dl .20 1 P41 -SW-192 Al-r 3 P41 Lugs AUG OWN PRE D -A HI 1 P41 -SW-193 All' C-37A IS1 Dl .20 1 P41 -SWH-193 All' 3 P41 Lugs AUG OWN PRE D A H1 1P41-SWH-194 AT C-37A IS1 Dl .20 1 P41 -SWH-194 Al-r Lugs AUG 3 P41 OWN PRE D A HI 1 P41 -SWH-20 All' C-22 ISI Dl .20 1 P41 -SWH-20 ATT Lugs AUG 3 P41 OWN PRE D -A H1 1 P41 -SW-232 ATT C-37A IS1 Dl .20 1 P41 -SWH-232 AT LUGS AUG 3 P41 OWN PRE Page 13 - 14 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 3 IS1 Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I CornplD / System Scope / Method I Procedure Code Case D -A HI 1 P41 -SWH-260 All C-120 IS1 Dl .20 1 P41 -SWH-260 All Anchor AUG 3 P41 OWN PRE D -A HI 1 P41 -SWH-269 All C-39 IS1 Dl .20 1 P41 -SWH-269 All Lugs AUG 3 P41 OWN PRE D -A HI 1P41-SWH-274 All C-22 IS1 Dl .20 1 P41 -SWH-274 All Lugs AUG 3 P41 OWN PRE D -A HI 1 P41-SWH-290 All ISlll C-36 IS1 Dl .20 1 P41 -SWH-290 All Lugs AUG 3 P41 OWN PRE D -A HI 1 P41-SWH-711 ATT C-21 IS1 Dl .20 1 P41 -SWH-711 All Lugs AUG 3 P41 OWN PRE D -A HI 1 P41-SWH-712 All C-21 IS1 Dl .20 1 P41 -SWH-712 All Lugs AUG 3 P41 OWN PRE Page 14- 14 Period 1 Period 2 1125'2006 I Period 3 (D r. 2 2 5 5 ---- ---- ---- ---- ---- ---- ---- ----

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 1 of 14 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 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, po rtions of supports that are inaccessible by being encased in concrete, buried undergr ound, 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-1, 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 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 2 of 14 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 1 Basis Doc -Supports.doc Page 3 of 14 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 to 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 1 Basis Doc -Supports.doc Page 4 of 14 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" for Schedule 80 and Schedule 160 water lines.

NPS 2" for Schedule 80 steam lines a nd NPS 2.5" for Schedule 160 steam lines.

Per Schedule Works there are 71 Category F-A, Item F1.10 piping supports (excluding snubbers). It should be noted that, in many cases, the HNP-1 design isometric 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. These are: X-7A-D, X-9A&B, X-10, X-11, X-12, X-13A&B, X-14, X-16A&B, and X-17. (Note: X-11, X-13B, X-14, and X-16B were examined during the 3 rd Interval, prior to development of this document; however, they are not credited).

Table IWF-2500-1, Category F-A, Item F1.10 re quires that 25% of the 71 (or 18) non-exempt Class 1 supports be examined. 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 elim inate 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 18 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 B21 30 7.5 7 B31 8 2 2 E11 11 2.75 3 E21 10 2.5 2 E41 7 1.75 2 E51 2 0.5 1 G31 3 0.75 1 TOTAL 71 17.75 18

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 5 of 14 Rev. 1 Additionally, these same systems have snubbers. While the examination of the snubber unit is performed per OM, not Section XI; the remainder of the s upport is effectively examined the same as any other support. As shown in the table below, there are 54

snubbers in Class 1; therefore, 14 require examination per Section XI. The 14 snubbers are prorated through the Class 1 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 B21 23 5.75 5 B31 9 2.25 2 E11 10 2.5 3 E21 0 0 0 E41 7 1.75 2 E51 1 .25 1 G31 4 1 1 TOTAL 54 13.5 14

Because of the potential changes in the snubber population during the 4 th Interval, one additional snubber has been added to the examination scope to account for any variances.

This would allow the addition of four Cla ss 1 snubbers before there would be a Code issue. This additional snubber is a B21 snubber.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 6 of 14 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-1).

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-1).

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-1). Portions of supports that are inaccessible by being encased in concrete, buried underground, or encapsulated by guard pipe.

Per Schedule Works there are 359 non-exempt Category F-A, Item F1.20 piping supports (excluding snubbers).

It should be noted that, in many cases, the HNP-1 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 359 non-exempt Class 2 supports (or 54) 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 55 examinations were performed.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 7 of 14 Rev. 1 CLASS 2 (Item F1.20) System No. of Non-Exempt Supports in

System Calculated No. of Supports Examined No. of Supports Selected E11 137 20.55 21 E21 49 7.35 7 E41 86 12.9 13 E51 4 0.60 1 G51 1 0.15 1 N11 48 7.2 7 P41 18 2.7 2 T48 16 2.4 2 TOTAL 359 53.85 54

Additionally, these 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 s upport. As shown in the table below, there are 91 snubbers in Class 2; therefore, 14 require examination per Section XI. The snubbers are prorated through the Class 2 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 E11 45 6.75 7 E21 3 0.45 1 E41 19 2.85 2 E51 3 0.45 1 N11 15 2.25 2 T48 6 0.9 1 TOTAL 91 13.65 14

Because of the potential changes in the snubber population during the 4 th Interval, one additional snubber has been added to the examination scope to account for any variances.

This would allow the addition of six Class 2 snubbers before there would be a Code issue. This additional snubber is an E41 snubber.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 8 of 14 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-1).

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-1).

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

Per Schedule Works there are 247 non-exempt Category F-A, Item F1.30 piping supports (excluding snubbers).

It should be noted that, in many cases, the HNP-1 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 247 non-exempt Class 3 supports be examined. Therefore, at least 25 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 25 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 B21 34 3.4 4 E11 79 7.9 8 E51 20 2 2 P41 114 11.4 11 TOTAL 247 24.7 25

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 9 of 14 Rev. 1 Additionally, these 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 s upport. As shown in the table below, there are 37 snubbers in Class 3; therefore, 4 require examination per Section XI. The 37 snubbers 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 31 3.1 3 E11 6 0.6 1 TOTAL 37 4 4

Because of the potential changes in the snubber population during the 4 th Interval, one additional snubber has been added to the examination scope to account for any variances.

This would allow the addition of 10 Class 3 snubbers before th ere would be a Code issue.

This additional snubber is an E11 snubber.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 10 of 14 Rev. 1 Determination of Supports Other Than Piping to be Examined Per Schedule Works there are 54 non-exempt Category F-A, Item F1.40 equipment supports. These 54 supports are shown in the below listed table. requires the examination of each equipment support except when there are multiple components within a system that have a similar design, func tion, 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 shown in the below listed table.

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.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 11 of 14 Rev. 1 Equipment Supports (Excluding Snubbers) Item F1.40Component Fig Description P1 P2 P3 Notes 1. 1B11-A001-S01 RPV Skirt S 2. 1B31-HA5 RC PUMP A - SPRING

3. 1B31-HA6 RC PUMP A - SPRING

4. 1B31-HA7 RC PUMP A - SPRING

5. 1B31-HB5 RC PUMP B - SPRING S 6. 1B31-HB6 RC PUMP B - SPRING S 7. 1B31-HB7 RC PUMP B - SPRING S 8. 1C41-A001-S01 Tank S 9. 1C41-C001A-S01 SBLC Pump S 10. 1C41-C001B-S01 SBLC Pump

11. 1E11-B001A-S01 RHR Heat Exchanger S 12. 1E11-B001B-S01 RHR Heat Exchanger

13. 1E11-C002A-S01 RHR Pump S 14. 1E11-C002B-S01 RHR Pump 15. 1E11-C002C-S01 RHR Pump 16. 1E11-C002D-S01 RHR Pump 17. 1E21-C001A-S01 CS Pump S 18. 1E21-C001B-S01 CS Pump 19. 1E41-C001-S01 HPCI Pump S

20. 1E51-C001-S01 RCIC Pump S

21. 1T47-B007A-S01 Cooling Unit S 22. 1T47-B007B-S01 Cooling Unit

23. 1T47-B008A-S01 Cooling Unit S 24. 1T47-B008B-S01 Cooling Unit

25. 1T47-B009A-S01 Cooling Unit S 26. 1T47-B009B-S01 Cooling Unit

27. 1E11-C001A-S01 RHRSW Pump S 28. 1E11-C001A-S02 RHRSW Pump S 29. 1E11-C001B-S01 RHRSW Pump

30. 1E11-C001B-S02 RHRSW Pump

31. 1E11-C001C-S01 RHRSW Pump

32. 1E11-C001C-S02 RHRSW Pump

33. 1E11-C001D-S01 RHRSW Pump

34. 1E11-C001D-S02 RHRSW Pump

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 12 of 14 Rev. 1 Equipment Supports (Excluding Snubbers) Item F1.40Component Fig Description P1 P2 P3 Notes 35. 1E11-D002A-S01 RHRSW Strainer S 36. 1E11-D002B-S01 RHRSW Strainer

37. 1E11-D003A-S01 RHRSW Strainer S 38. 1E11-D003B-S01 RHRSW Strainer

39. 1P41-C001A-S01 PSW Pump S 40. 1P41-C001A-S02 PSW Pump S 41. 1P41-C001B-S01 PSW Pump 42. 1P41-C001B-S02 PSW Pump 43. 1P41-C001C-S01 PSW Pump 44. 1P41-C001C-S02 PSW Pump 45. 1P41-C001D-S01 PSW Pump 46. 1P41-C001D-S02 PSW Pump 47. 1P41-D103A-S01 PSW Strainer S 48. 1P41-D103B-S01 PSW Strainer

49. 1T41-B002A-S01 RHR/CS Room Cooler S 50. 1T41-B002B-S01 RHR/CS Room Cooler

51. 1T41-B003A-S01 RHR/CS Room Cooler S 52. 1T41-B003B-S01 RHR/CS Room Cooler

53. 1T41-B005A-S01 HPCI Room Cooler S 54. 1T41-B005B-S01 HPCI Room Cooler TOTAL 54 Additionally, the Recirculation Pumps 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. There are six snubbers on each pump, with only the snubbers on one pump requiring examination.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 13 of 14 Rev. 1 TOTAL CLASS 1, 2, AND 3 PIPING SUPPORTS AND EQUIPMENT SUPPORTS Code Case N-598 requirements were met as shown in the Code Compliance Scheduling Summary for F-A supports and snubbers.

HATCH UNIT 1 FOURTH INTERVAL ISI PLAN COMPONENT SUPPORTS Hatch 1 Basis Doc -Supports.doc Page 14 of 14 Rev. 1 RE-EXAMINATION OF SUPPORTS When a support must be subjected to corrective measures in acco rdance with Section -

2420 of Code Case N-491, the support shall be re-examined during the next inspection period. Interpretation XI-1-86-30R may be used to eliminate the re-examination requirement provided that the support has been analyzed and/or tested to substantiate its integrity for its intended service, and has been found to be acceptable.

Interpretation Number: XI-1-86-30R Date: 08-MAR-95

Subject:

Section XI, IWF-2430, IWF-2420 (b), and IWF-3000; Visual Examinations of Supports and Corrective Measures (1980 Edition and Later Addenda and Editions Through the 1993 Addenda)

Question: Is it the intent that when an inservice examination of a component support reveals conditions described in IWF-3410(a), and the component support has been analyzed and/or tested to substantiate its integrity for its intended service, and has been found to be acceptable, that additional support examinations be required by IWF-2430 or successive examinations be required by IWF-2420(b) when and Owner chooses to perform corrective measures for the purpose of restoring the support to its original design condition?

Reply: No.

SNC uses an Indication Notification Form (INF) to report to document when supports require evaluation to substantiate their integrity for their intended service. INFs for a given 40-month Period should be reviewed to ensure that any required re-examinations during the next 40-month Period are sc heduled. For the start of the 4 th Interval only those INFs written during the 3 rd Period of the 4 th Interval would require re-examination in the 1 st Period of the 4 th Interval. There are no 3 rd Interval, 3 rd Period INFs applicable to supports.

Southern Nuclear Operating Company Page 1 - 21112006 Code Compliance Scheduling Summary - 4th Interval IS1 - Code Edition - 2003 Addenda PERIOD 1 PERIOD 2 PERIOD 3 ACTUAL ROUND COUNT PERIOD UP 6 101.41% 100% 5 111.11% 108% 19 102.14% 102% 5 109.89% 108% 11 101.21% 100% 2 135.14% 125% 20 133.33%

134% 0 100.00% 100% 68 106.00%

106% PERCENT ACTUAL ROUND TOTAL CAT ITEM CODECASE POPULATION REQUIRED REQUIRED UP EXAMS F-A F1.10 7 1 25% 17.75 18 18 F-A F1.1OS 54 25% 13.5 14 15 F-A F1.20 359 15% 53.85 54 55 F-A F1.20S 9 1 15% 13.65 14 15 F-A F1.30 247 10% 24.7 25 25 F-A F1.30S 37 10% 3.7 4 5 F-A F1.40 54 33.33%

18 18 24 F-A F1.40S 12 50% 6 6 6 Total: 925 153 153 163 ACTUAL ROUND COUNT PERIOD UP 5 28.17% 28% 4 29.63% 29% 14 26.00% 26% 3 21.98% 22% 4 16.19% 16% 1 27.03% 25% 1 5.56% 6% 3 50.00% 50% 35 22.80%

23% ACTUAL ROUND COUNT PERIOD UP 7 67.61% 67% 6 74.07% 72% 22 66.85% 67% 7 73.26% 72% 10 56.68% 56% 2 81.08% 75% 3 22.22% 23% 3 100.00% 100% 60 62.00%

62%

Revision:

1 HNP-1 Fourth Interval Class 1 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Cornp. Desc. Class Summary I ComplD I System Scope 1 Method I Procedure Code Case F -A HI 1 B21-FDH-7 IS IIVTI A-1 3 IS1 F1.10 1821 -FDH-7 SPRING AUG 1 821 OWN PRE FA HI 1 B21-FDH-8 A-8 IS1 F1.10 1 B21 -FDH-8 STRUT AUG 1 821 OWN PRE F -A HI 1 B21-FDH-9 A-8 IS1 F1.10 1821 -FDH-9 RESTRAINT AUG 1 821 OWN PRE FA HI 1B21-GA1 A-4A IS1 F1.10 1 B21 -GA1 RESTRAINT AUG 1 821 OWN PRE FA H1 1821-GB1 ISINTINMP-ES-024-201 A-5A IS1 F1.10 1 B21 -GB1 RESTRAINT AUG 1 821 OWN PRE FA H1 1B21-GC1 A-6A IS1 F1.10 1 B21 -GC1 RESTRAINT AUG 1 821 OWN PRE F -A HI 1B21-GD1 A-7A IS1 F1.10 1 821 -GD1 RESTRAINT AUG 1 821 OWN PRE FA HI 1821-HA1 A-4 IS1 F1.10 1 821 -HA1 SPRING AUG 1 821 OWN PRE FA HI 1 B21-HA2 A-4 IS1 F1 .I0 1 B21 -HA2 SPRING AUG 1 821 OWN PRE FA HI 1B21-HA3 A-4 IS1 F1.10 1821 -HA3 SPRING AUG 1 821 OWN PRE Page 2 - 8 Period 1 Period 2 Period 3 Revision:

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

Class Summary I ComplD I System Scope I Method 1 Procedure Code Case FA HI 1821-HB1 A-5 IS1 F1 .I0 1 821 -HB1 SPRING AUG 1 82 1 OWN PRE F-A H1 1 821-HB2 A-5 IS1 F1.10 1 821 -H82 SPRING AUG 1 821 OWN PRE F -A HI 1 821 -H83 ISIII A-5 IS1 F1.10 1 821 -HB3 SPRING AUG 1 821 OWN PRE F -A H1 1821-HC1 A-6 IS1 F1.10 1821-HC1 SPRING AUG 1 82 1 OWN PRE F-A H1 1821-HC2 A-6 IS1 F1.10 1821 -HC2 SPRING AUG 1 821 OWN PRE F -A HI 1821-HC3 ISIII A-6 IS1 F1.10 1 821 -HC3 SPRING AUG 1 821 OWN PRE F -A HI 1821-HD1 A-7 IS1 F1.10 1821-HD1 SPRING AUG 1 821 OWN PRE F -A HI 1 821-HD2 A-7 IS1 F1.10 1 821 -HD2 SPRING AUG 1 821 OWN PRE FA HI 1821-HD3 A-7 IS1 F1.10 1821 -HD3 SPRING AU G 1 821 OWN PRE F -A H1 1 821-TORSION-LATERAL A-8 IS1 RESTRAINT AU G OWN PRE Page 3 - 8 Period 1 Period 2 Period 3

LZNHC 9ZNHC SZ'HC VZNHC SZNHC 11111,111

,111 111,1111111111,111111111111111111

~ZZ~HCm~~8~a~~~~mmoo~88~~#b~~~~~~~~~~~~1~~

am Z ,,,11,,,,, 1,111111 I- Z_ a K I- a K 0 C MOO E s '0 a U ,,,,,,11111,,11111111111111111111111

~~~M~MM~~M~M~~~~~~~~~~~~~~~

~~DM#~~~~~##~~~~~~#~#~~~~M~#~M 1111111111111111111111111111111111111111

~VV~~~~V~M~M~O~V~M~III~~~~~!~

~~III~o~~~II~!o~~M~~~~~~~M~M

~~MMMM~~MMMMM~~~~~~~~~~~~~~I 1,111 11,,,1,111111,,,, W %' J = >; QK m 0 I- Z .- 111111111111~1111111111111, 111111111111111 b o 0 0 .- ? F; K u; - m- fC8 0 5 Y C7 z K fl w rn F; K u; - m .- fCC; - g 8 u, - m 5r u, . E 1111111111111111,,,,, Z P 2 2 3 ,,,,,,,, 1,1111, I- Z Q K I- m w rn I- Z Q K I- n3 0 v w Q K C7 z 0 K a3 .- C7 z 0 K a, .- C7 z fl K 7 i I- z Q K I- fl m 3 fl

LZHHL ~ZHHL SZHHL VZHHL - EZHHL ~ZZ~H~~~~~~~~~DI~DD~~~~~~~~~~D~~~~~~~~~~~~~~~~

Li wo ow I,, ,1111 ~~oo~~~oo~~~!!~~oo~~~~

~~,,,,DD~~~~o~~D~~~~~~~~,,, 1111111111111111111IIIIIIIIIIIIIIIJIIII!

~~~~~~~~m8om~~~~~~~o!!8~~~~~~~~#~#mar~

~M~M~~M~~~M~!~~~~~~~~#!!~!#~~~

11111111111111111111111111111llllI1 11111111,1111111111111111111111111111111 r,~~~~m~~m~~~~~,D,8

,,,,,,,,,, ,,,,,,,,,, I,,,,,, 111111111111111111111111111111 IIIIIIIIIIII~IIIIIIIII~IIIII IIIIIIIIIIIIIIIIIIIIIIIIIII,,, IT W m m 3 Z : F U 2 L \ w 0 5 f \ 0 n 0 U V) E

• w % V) - P n 2 Lt.= -0 m E 25 7 - -2 v)I.-~ vrvuLL- IT W m m 3 Z cn IT n - > k I r. 7 x n ; 9 n 5 7 - N- -mN I.-m 2 7 ? - YLL- IT W m m 3 Z 0 IT N n - > k I s 2 co 7 9 m n 9 n 2 5 7 - N- -ma I-m cn z ? - YLL- IT W m m 3 Z cn IT - n - > k I m 7 9 n LL lo x 2 5 7 - N 7 -mN I.-m (I) 0 7 ? - YLL- IT W m m 3 Z cn I N o - w k r 0 2 5 7 - N 7 -mN I.-m 0 0 7 ? - YLL- IT W m m 3 Z cn IT - n - > k I 7 2 5 7 - N - -mN I-m (I) 0 7 ? - YLL- IT W m m 3 Z cn IT c-7 n - > k I s V, ln T ln n c-4 5 9 - n 2 5 - s 7 .-mN I.-m 0 z ? .i YLLr IT W m m 3 Z cn IT c-7 n - > k I w 2 w n fl 9 L n 2 5 7 - N- 2 (I) 2 ? - ILL.- IT W m m 3 Z cn I IT W m m 3 Z cn I o co w k r s V, 0 0 z z n r. 9 L n 2 5 7 - N 7 -ma I-m 0 0 7 ? - YLL- o o - w 4 r Q, 0 b 5 I0 n r- 5 9 - n 2 5 - - N 7 5C2 0 0 7 ? - YLL-Revision:

1 HNP-1 Fourth Interval Class 1 Snubber Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope I Method I Procedure Code Case F -A HI 1 B21 -FDH-701 B A-10 IS1 F1 .IOS 1821-FDH-701B MECH SNUBBER AUG 1 821 OWN PRE F -A HI 1821-FDH-829 A-1 1 IS1 F1 .lOS 1 821 -FDH-829 HYDR SNUBBER AUG 1 821 OWN PRE F -A HI 1 B21-RCIC-SS-41 ISlll A-30 IS1 F1 .lOS 1821-RCIC-SS-41 HYDR SNUBBER AUG 1 821 OWN PRE F -A H1 1 B21-RCIC-SS-42 A-30 IS1 F1.1OS 1821 -RCIC-SS-42 HYDR SNUBBER AUG 1 821 OWN PRE F -A HI 1 B21-RClC-SS-43 A-30 IS1 F1 .lOS 1 B21-RCIC-SS-43 HYDR SNUBBER AUG 1 82 1 OWN PRE F -A H1 1821-RCIC-SS-44 A-30 IS1 F1 .lOS 1821-RCIC-SS-44 HYDRSNUBBER AUG 1 821 OWN PRE F -A HI 1821-SS1 lSlll A-4 IS1 F1 .lOS 1821 -SS1 HYDRSNUBBER AUG 1 821 OWN PRE F -A HI 1B21-SS2 A-4 IS1 F1.1OS 1 B21-SS2 HYDRSNUBBER AUG 1 821 OWN PRE F -A HI 1 B21-SS23 A-6 IS1 F1 .lOS 1 821 -SS23 HYDRSNUBBER AUG 1 821 OWN PRE F -A H1 1021-5524 A-6 IS1 HYDRSNUBBER AUG OWN PRE Page 2 - 6 Period 1 Period 2 Period 3 LZHHC 9ZHHC SZHHI, PZHHC u' II,IIIIIIII,,IIIIIIIIIIIIIIIIIIIJII IIIIIIIIIJIIIIIIIII11111111111111111 I,,,, ,,,I rr ~D~M~vHM~~~M~~~E~o~~MI~~DD~D~~~~

111111,1111111,111llllll1ll11,,,,,,,,,,, 111111111111111111111111111111111111111, ~~DD~O~~~~~~WIODD~~~~~~~~~~~

m 0 .- 2 0 %hl ? z % - .- 0 0 Gi i; 0 & 0 m 0 m 0 g ? 0 0 $! L 5 L m . 7 - $!: m .- m .- -mm -mm -mm -mm I.-m I.-m I.-m I.-m s z 0 0 0 0 0 0 0 0 0 0 0 rr r- "oo c L 3 u U 0 L n . u 0 5 z . c IIIIIIIIII,IIIIIIII,IIIII,IIIIIIII IIIIIIIIIIIIIIIIIIIJIIIIIIIIIIIIII

~Z~H~W~IM~M~~~~M~~MDM~~~IM~~~~~~~

~ZZ~HCD~~~~D~~~~~ID~~~~~~~D~~~~~~~~~~~~~D~~~~~

41 I,,,,, ,,,I,, rr a I cn f C V) % cn . P rr W m m 0 m rr hl 2 0 (L, rr W m m 3 Z 0 m rr k I 0 rr W m m 3 Z 0 I b 0 - W k r r- rr W m m 3 Z 0 rr . . - 2 rr W m m 3 Z 0 m rr l.0 0 - > 4 I hl 7 rr W m m 3 Z 0 0 m rr l.0 0 - > a I m 0 m rr rr W m m 3 Z rr W m m 3 Z rr W m m 3 Z rr W m m 3 Z LZHHC gZHHC PZJHC CZHHC 6 via I,,,, 11 I,,,, ,,,, K K W m m 3 K o - > k I CO m .- z "? 7 - m - - ? - YLL- "00 z a F 0 2 n . u 0 5 . 0 n 2 v, E 0 C) r v, . E n EZHHLmnmmvnn~118nnnn~~nntt,~

II,,IIIII,IIIIIII,IIIIIIIIIIIIIII eZZ~HC~#~o~~~~~~~oo88~~~mm#~8~~~~#~~,~~~~~~~~~

kI 2 L!? K W m m 3 z (I) K - o s (I) - 7 "? 7 7 z "? 7 - 7 7 w- I.-W (I) 0, ? - YLL- I,,,,IIII,IIIIIIIJ!IIIIIIIIIIIIIIJIIIIII ,I,,,,,IIIIIIIIIIIIIIIIIIII!IIIIIIIIIIII

~~~8~o~~~~~~~~m~~88~~~oooo#t8~~880tto~~~

~8~#~t~m~~v8~~~~~8~m~~~~~~

1111111111111111111111111111111111111111 mo~~~~~~~~~t~##~~~r~~~~~~~~~~~~o~r 1111111111111111111111111111

~~M~~~~~~~~M~~U~~~D~~~~~~VM E z"? E -s.- a -mm K W m m 3 Z (I) LT N o 7 > a I ? "? In 7 7 z "? .- - .- 7 -W' I.-W 7 ? - YLL- s; z 0 IIIIIIIIIIIIIIIIIIIIIIIIIII,,, (I) I,,,,,, 1,111, K W m m 3 Z (I) K - o N "? 7 N - (I) % 7 r -w- I.-W V) z ? YLL- OrOLLL- K W m m 3 Z (I) K a I * "? 7

• z "? 7 - 7 7 -w- I.-W (I) z ? - YLL- K W m m 3 Z (I) K - o In "? 7 In z "? 7 - 7 7 -w- I.-W (I) z ? YLL- K W m m 3 Z (I) K N o 7 > a I 2 L!? 7 I "? 7 7 2 z "? 7 - 7 7 'W' I.-W 0 z ? - YLL- K W m m 3 Z (I) K 2 L!? 7 H "? 7 7 3 - "? % 'W' I.-W (I) z 4, YLL- K m o 7 > a I 3 I "? 3 7 2 L"? 7 - 7 7 'W' 1.-W - ? - YLL- K W m m 3 z (I) K W m m 3 Z (I)

Revision:

1 HNP-1 Fourth Interval Class 1 Snubber Plan Southern Nuclear Operating Company Page 6 - 6 112612006 1 Period 1 Period 2 Period 3 ah 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. IternNO, Cornp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case FA HI 1G31-S17 A-32 IS1 F1.lOS 1G31-S17 HYDR SNUBBER AUG 1 G31 OWN PRE FA HI 1 G31 -SM-5 A-32 IS1 F1 .IOS 1 G31-SM-5 SNUBBER AUG 1 G31 OWN PRE FA HI 1 G31-SM-6 ISlll A-32 IS1 F1.l OS 1 G31 -SM-6 MECH SNUBBER AUG 1 G31 OWN PRE F -A HI 1G31 -SM-7 A-32 IS1 F1 .I OS 1 G31 -SM-7 HYDR SNUBBER AUG 1 G31 om PRE P3 2 2 5 I- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 5 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -----s------ - - - - - - - - - - - - ------------ - - - - - - - - - - - -

Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A HI 1 El 1-RHRH-147 6-62 IS1 F1.20 1 El 1 -RHRH-147 SPRING AUG 2 El 1 OWN PRE F-A HI 1El1-RHRH-148 6-62 IS1 F1.20 1 El 1 -RHRH-148 SPRING AUG 2 El 1 OWN PRE F -A HI 1El1-RHRH-15 6-41 IS1 F1.20 1 El 1 -RHRH-15 SPRING AUG 2 El 1 OWN PRE F -A HI 1 El l-RHRH-153 6-72 IS1 F1.20 1 El 1 -RHRH-153 SPRING AUG 2 El 1 OWN PRE F -A HI 1 El I -RHRH-154 6-72 IS1 F1.20 1 El l-RHRH-154 SPRING AUG 2 El 1 OWN PRE FA H1 1El1-RHRH-16 6-41 IS1 F1.20 1 El 1-RHRH-16 SPRING AUG 2 El 1 OWN PRE FA HI 1E11-RHRH-17 6-41 IS1 F1.20 1 El 1-RHRH-17 SPRING AUG 2 El 1 OWN PRE FA HI 1 El 1-RHRH-18 ISI/VT/NMP-ES-024-203 6-41 IS1 F1.20 1 El 1 -RHRH-18 ANCHOR AUG 2 El 1 OWN PRE FA HI 1E11-RHRH-19 6-34 IS1 F1.20 1 El 1-RHRH-19 SPRING AUG 2 El 1 0 WN PRE F -A HI 1 El 1-RHRH-190 6-39 IS1 F1.20 1 El 1 -RHRH-190 RESTRAINT AUG 2 El 1 OWN PRE Page 2 - 36 Period 1 Period 2 Period 3

Revision:

1 Category, IternNO, HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Iso No. Cornp. Desc. Class Summary I CornplD I System Scope I Method I Procedure Code Case F -A HI 1 El 1-RHRH-209 8-53 IS1 F1.20 1 El 1 -RHRH-209 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-21 8-34 IS1 F1.20 1 El 1 -RHRH-21 SPRING AUG 2 El 1 OWN PRE F -A HI 1 El 1 -RHRH-219 ISI/VT/NMP-ES-024-203 8-46 IS1 F1.20 1 El 1 -RHRH-219 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-22 lSl// 8-35 IS1 F1.20 1 El 1 -RHRH-22 SPRING AUG 2 El 1 OWN PRE F -A HI 1 El 1 -RHRH-222 8-49 IS1 F1.20 1 El 1-RHRH-222 RIGID SUPPORT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-23 8-37 IS1 F1.20 1 El 1 -RHRH-23 SPRING AUG 2 El 1 OWN PRE F -A H1 1 El 1-RHRH-232A8B 8-45 IS1 F1.20 1 El 1 -RHRH-232A88 RIGID SUPPORT AUG 2 El 1 OWN PRE F -A HI 1Ell-RHRH-235 8-52 IS1 F1.20 1 El 1 -RHRH-235 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El 1 -RHRH-236 8-52 IS1 F1.20 1 El 1 -RHRH-236 ANCHOR AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-239 8-52 IS1 F1.20 1 El 1 -RHRH-239 RIGID SUPPORT AUG 2 El 1 OWN PRE Page 4 - 36 112612006 1 Period 1 Period 2 Period 3 LZ'HC CJZMHC SZMHC VZMHC CZMHL 11,1111 6 V) al al In nm ,1111 ~ZZ~HC88~~~~o~~mmmmo~~~~~~~~##~~o~~~~

IIIIIII,,, ,,,,,,,,,, ,,,,,,,,,, ,,,,,,,,,, K W ~~~M~M~~M~M-M~M~~MU~~~~~

~~~a~uv~~~~8~~~~o~~8~~~~o~~~~~~~

1111111111111111111111111111111111111111

~~~mmv~$~~t#~~M~M~Omo~~~~~

s~o~omm~8##~~~#~~~m1#8~~~#####~~~~~~8~~a 111111111111111111111111111111111II

~M~M~~~M~M~M~M~~M~MII~~~~~~

z 3 u al 0 L n \ u 5 \ al n 0 V) f C V) V) \ + z_ a K + c-4 0 IIIIIIIIIIIIIIIIIIIIIIIIIIIIII 11111111111111111111111,11III, 1111111111111111111111111111,1 I

• i 8 v I m K l-4 2 0 I I I I I i I I v I I K T I I K K K K K ; I A I ;; 9 7 - 9 s; 5 0 0 N 0 0 0 0 0 N 0 N 0 N N 0 =? .l =? ? =? .l =? n! 7 ? =? n! - LLLN LLLN LLLN LLUN LLLN LLLN LLLN LLLN LLLN ? w m K 11111111111111111111111 rr 0 I 0 0 m

• v m + z_ a K + - tn r. K 0 I - 0 8 N 0 z mrr 3 a m tn m 0 z_ 3 a m tn (D 0 z co + z a K + 0 z_ K m rr a 0 UZ a m tn o Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary / ComplD I System Scope I Method I Procedure Code Case F -A HI 1E11-RHRH-304 8-56 IS1 F1.20 1 El I -RHRH-304 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-308 ISllVT/NMP-ES-024203 8-35 IS1 F1.20 1 El 1 -RHRH-308 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1Ell-RHRH-31 ISIII 8-53 IS1 F1.20 1 El 1 -RHRH-31 SPRING AUG 2 El 1 OWN PRE F -A H1 1El1-RHRH-311 8-34 IS1 F1.20 1 El 1 -RHRH-311 RESTRAINT AUG 2 El I OWN PRE F -A HI 1El l-RHRH-314 8-37 IS1 F1.20 1 El 1 -RHRH-314 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1El1-RHRH-315 8-37 IS1 F1.20 1 El 1 -RHRH-315 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El I -RHRH-317 8-34 IS1 F1.20 1 El 1 -RHRH-317 RESTRAINT AUG 2 El 1 OWN PRE F-A H1 1 El 1 -RHRH-318 8-72 IS1 F1.20 1 El 1 -RHRH-318 ANCHOR AUG 2 El 1 OWN PRE FA HI 1 El l-RHRH-32 8-55 IS1 F1.20 1 El 1 -RHRH-32 SPRING AUG 2 El 1 OWN PRE F -A H1 1 El 1-RHRH-326 ISINTINMP-ES-024203 8-38 IS1 F1.20 1 El 1 -RHRH-326 RESTRAINT AUG 2 El 1 OWN PRE Page 6 - 36 Period 1 Period 2 Period 3 LzHHL SZHHL VZHHL SZHHL ~Z~HL~~~~~M~MMW~~M~MMM~~~~#O##

~ZZ~~~~8t~88~~~~b~~8~88floo##8~~88~~~~ba~~t~~~~

ri V) al $0 I,,,,,, 1,11111 ,,,,,,,,, IIIIIIIIIIIIIIIIIIIIIIIIJIIIIIIII 1111111111111111111116111111111111111111

~~~~~~~~~~~~~~~~~~~8~~~~~~~~~~~~~~~~~~~~

1111111111111111111111111111111111111111

~MMM~o~~M~M~~~~~OOO~~~D~~~~~

~~~m~~~~~~~8~mmmo~~~~~~~bm 1111111111111111111111111111111111111111 11111111111111111111111111111111~

~~~M~o~~MM~~o~~~~~~~MM~~

1111111111111111111~11111111111 C3 z 4 200 f! a u U E n . u 5 . al 0. U V) C V) ZI V) . - 9 W - i b 0 0 0 0 3 a m v, mv, 4 z Ln 3 I- z a rr I- v, . 1 - 0 I- z a rr m rr P w I- z a rr I- CO v, rr 2% C3 z rr I- z a rr I- In 0 C3

• 2 C3 z

Revision:

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

Class Summary I ComplD /System Scope I Method I Procedure Code Case F -A HI 1 El 1-RHRH-45 8-47 IS1 F1.20 1 El 1 -RHRH-45 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-46 8-56 IS1 F1.20 1 El 1 -RHRH-46 HANGER AUG 2 El 1 OWN PRE F -A H1 1 El 1-RHRH-47 8-56 IS1 F1.20 1 El 1 -RHRH-47 HANGER AUG 2 El 1 OWN PRE F -A H1 lE11-RHRH-47A 8-56 IS1 F1.20 1 El 1 -RHRH-47A SPRING AUG 2 El I OWN PRE F -A HI 1 El 1-RHRH-48 8-56 IS1 F1.20 1 El 1-RHRH-48 SPRING AUG 2 El 1 OWN PRE FA HI 1E11-RHRH-48A 8-63 IS1 F1.20 1 El 1 -RHRH-48A HANGER AUG 2 El 1 OWN PRE F -A H1 lE11-RHRH-49 8-49 IS1 F1.20 1 El 1 -RHRH-49 SPRING AUG 2 El 1 OWN PRE F -A H1 1 El 1-RHRH-52 8-46 IS1 F1.20 1 El 1 -RHRH-52 HANGER AUG 2 El 1 OWN PRE F -A HI 1 El 1 -RHRH-53 ISI/VT/NMP-ES-024203 8-46 IS1 F1.20 1 El 1 -RHRH-53 HANGER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-53A 8-46 IS1 F1.20 1 El 1 -RHRH-53A SPRING AUG 2 El I OWN PRE Page 9 - 36 Period 1 Period 2 Period 3

Revision:

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

Class Summary I ComplD I System Scope I Method I Procedure Code Case F-A HI 1 El 1-RHRH-67 6-61 IS1 F1.20 1 El 1-RHRH-67 HANGER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-68 6-61 IS1 F1.20 1 El 1 -RHRH-68 RESTRAINT AUG 2 El 1 OWN PRE F -A H1 1 El 1-RHRH-69 6-61 IS1 F1.20 1 El 1-RHRH-69 HANGER AUG 2 El 1 OWN PRE FA HI 1 El 1-RHRH-71 6-61 IS1 F1.20 1 El 1 -RHRHJl HANGER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-710 6-36 IS1 F1.20 1 Ell-RHRH-710 SUPPORT AUG 2 El 1 OWN PRE F -A H1 1 El 1-RHRH-712 6-36 IS1 F1.20 1 El 1 -RHRH-712 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-714 6-42 IS1 F1.20 1 El 1-RHRH-714 SUPPORT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-715 6-42 IS1 F1.20 1E11-RHRH-715 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1E11-RHRH-717 6-41 IS1 F1.20 1 El 1-RHRH-717 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-718 6-38 IS1 F1.20 1 El 1 -RHRH-718 HANGER AUG 2 El 1 OWN PRE Page 11 - 36 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD I System Scope 1 Method I Procedure Code Case F -A HI 1E11-RHRH-72 8-61 IS1 F1.20 1 El 1 -RHRH-72 SPRING AUG 2 El 1 OWN PRE FA HI 1 El l-RHRH-720 ISIII 8-39 IS1 F1.20 1 El 1-RHRH-720 HANGER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-723 8-5 IS1 F1.20 1 El 1 -RHRH-723 HANGER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-727 ISIII 8-57 IS1 F1.20 1El l-RHRH-727 SPRING AUG 2 El I OWN PRE F-A HI 1E11-RHRH-729 8-22 IS1 F1.20 1 El 1 -RHRH-729 RIGID SUPPORT AUG 2 El I OWN PRE F -A HI 1 El l-RHRH-73 8-65 IS1 F1.20 1 El 1 -RHRH-73 HANGER AUG 2 El 1 OWN PRE F -A HI 1E11-RHRH-731 8-63 IS1 F1.20 1 El 1 -RHRH-731 HANGER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-733 8-67 IS1 F1.20 1 El l-RHRH-733 RIGID SUPPORT AUG 2 El 1 OWN PRE F -A HI 1 El l-RHRH-74 8-65 IS1 F1.20 1 El 1 -RHRH-74 RESTRAINT AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-75 8-65 IS1 F1.20 1 El 1 -RHRH-75 HANGER AUG 2 El 1 OWN PRE Page 12- 36 Period 1 Period 2 Period 3 LzJHC gZJHC SZJHC WZJHC CZJHC ci ,,,1,,,,,,,,, ,,,,,,,,,, pZZJH~~#~8~~8~8811#888~~8#oo###oot88~~~8~~~~~~

I- w W (3

• z . . - V) - k I- z 200 f! a P U e n . '0 5 . al n U V)

• U) 2-u V) . 8111111JIIIIIIIIIII11111111111111141111t

~~~l~~~$~~~o~88000#~m~~#~~~~~~~8mm#~~~~t MMM~~~M~MM-M~M~MM~V~~~~O

,,,,11111,1111111111111111111111111~11,1

~m~~~~~~88~~~~~~v!~8~~~t~~tt~~~

~moo#~#t~~~1~888~~~~88~1~#488~~~~~~~#8#~

111111111111111111111111111111111111l~~~

,,,,,,111,,11111111111111111111111111111

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

Class Summary 1 ComplD I System Scope I Method I Procedure Code Case FA H1 1E21-CSH-18 8-2 IS1 F1.20 1 E21 -CSH-18 SPRING AU G 2 E21 OWN PRE F -A H1 1 E21-CSH-19 8-2 IS1 F1.20 1 E21 -CSH-19 SUPPORT AUG 2 E21 OWN PRE FA H1 1 E21-CSH-20 8-2 IS1 SPRING AUG OWN PRE F -A HI 1 E21 -CSH-21 8-3 IS1 SPRING AUG OWN PRE FA HI 1E21-CSH-22 8-5 IS1 HANGER AUG OWN PRE F-A HI 1 E21 -CSH-23 B-5 IS1 ANCHOR AUG OWN PRE F -A HI 1E21-CSH-24 8-4 IS1 HANGER AUG OWN PRE FA H1 1 E21-CSH-25 8-4 IS1 HANGER AU G OWN PRE FA H1 1 E21-CSH-26 8-7 IS1 SPRING AUG OWN PRE F -A HI 1E21-CSH-27 8-8 IS1 SPRING AUG OWN PRE Page 15 - 36 Period 1 Period 2 112612006 1 Period 3

Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD I System Scope I Method I Procedure Code Case FA HI 1E21-CSH-44 8-2 IS1 F1.20 1 E21 -CSH-44 RESTRAINT AUG 2 E2 1 OWN PRE FA HI 1 E21-CSH-45 B-1 IS1 F1.20 1 E21 -CSH-45 RESTRAINT AUG 2 E21 OWN PRE F -A H1 1 E21-CSH-46 8-2 IS1 F1.20 1 E21 -CSH-46 RESTRAINT AUG 2 E21 OWN PRE FA HI 1 E21 -CSH-54 ISllVTINMP-ES-024-203 8-7 IS1 F1.20 1 E21 -CSH-54 HANGER AUG 2 E2 1 OWN PRE F -A HI 1 E21-CSH-55 8-7 IS1 F1.20 1 E21 -CSH-55 RESTRAINT AUG 2 E21 OWN PRE FA HI 1 E21 -CSH-56 8-7 IS1 F1.20 1 E21 -CSH-56 RESTRAINT AUG 2 E21 OWN PRE FA HI 1 E21 -CSH-58 8 -7 IS1 F1.20 1 E21 -CSH-58 RESTRAINT AUG 2 E21 OWN PRE F -A HI 1 E21 -CSH-59 8-8 IS1 F1.20 1 E21 -CSH-59 RESTRAINT AUG 2 E21 OWN PRE F -A H1 1 E21 -CSH-60 8-7 IS1 F1.20 1 E21 -CSH-60 ANCHOR AUG 2 E21 OWN PRE F -A HI 1E21-CSH-61 8-9 IS1 F1.20 1 E21 -CSH-61 RESTRAINT AUG 2 E21 OWN PRE Page 17 - 36 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A HI 1 E21-CSH-62 B-9 IS1 F1.20 1 E21 -CSH-62 RESTRAINT AUG 2 E21 OWN PRE FA HI 1E21-CSH-63 8-9 IS1 F1.20 1 E21 -CSH-63 RESTRAINT AUG 2 E21 OWN PRE F -A HI 1 E21-CSH-64 B-9 IS! F1.20 1 E21 -CSH-64 RESTRAINT AUG 2 E21 OWN PRE F -A H1 1 E21 -CSH-65 8-9 IS1 F1.20 1 E21 -CSH-65 RESTRAINT AUG 2 E21 OWN PRE FA HI 1 E21 -CSH-68 8-3 IS1 F1.20 1 E21 -CSH-68 RESTRAINT AUG 2 E21 OWN PRE F -A HI 1 E21-CSH-69 8-3 IS1 F1.20 1 E21 -CSH-69 RESTRAINT AUG 2 E21 OWN PRE F-A HI 1 E21 -CSH-70 8-3 IS1 F1.20 1 E21 -CSH-70 RESTRAINT AUG 2 E21 OWN PRE FA HI 1 E21-CSH-72 8-3 IS1 F1.20 1 E21 -CSH-72 RESTRAINT AUG 2 E21 OWN PRE F -A HI 1 E21-CSH-73 8-5 IS1 F1.20 1 E21-CSH-73 RESTRAINT AUG 2 E21 OWN PRE F -A HI 1 E21 -CSH-74 8-4 IS1 RESTRAINT AUG OWN PRE Page 18 - 36 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A HI 1 E21-CSH-75 B-6 IS1 F1.20 1 E21 -CSH-75 RESTRAINT AUG 2 E21 OWN PRE F -A HI 1 E21 -CSH-76 B-6 IS1 F1.20 1 E21 -CSH-76 RESTRAINT AUG 2 E2 1 OWN PRE F -A HI 1 E21 -CSH-77 B-6 IS1 F1.20 1 E21 -CSH-77 ANCHOR AUG 2 E21 OWN PRE FA HI 1 E21-CSH-78 B-6 IS1 F1.20 1 E21 -CSH-78 RESTRAINT AUG 2 E2 1 OWN PRE F -A H1 1 E21 -CSH-8 B-1 IS1 F1.20 1 E21 -CSH-8 RESTRAINT AUG 2 E21 OWN PRE F -A HI 1 E21-CSH-9 ISlll B-1 IS1 F1.20 1 E21 -CSH-9 SPRING AUG 2 E21 OWN PRE F -A HI 1 E41-HPCIH-1 ISIIVTINMP-ES-024-203 B-13A IS1 F1.20 1 E41 -HPCIH-1 ANCHOR AUG 2 E41 OWN PRE FA HI 1E41-HPCIH-10 8-1 3 IS1 F1.20 1 E41 -HPCIH-10 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-11 8-1 3 IS1 F1.20 1 E41-HPCIH-11 SUPPORT AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-1 IA B-10 IS1 F1.20 1 E41-HPCIH-11A RESTRAINT AUG 2 E41 OWN PRE Page 19- 36 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A H1 1 E41-HPCIH-11 B ISllVTl B-10 IS1 F1.20 1 E41 -HPCIH-1 1 B SUPPORT AUG 2 E41 OWN PRE FA H1 1 E41-HPCIH-12 ISllVTINMP-ES-024203 B-10 IS1 F1.20 1 E41 -HPCIH-12 RESTRAINT AUG 2 E41 OWN PRE FA HI 1 E41-HPCIH-13A ISllVTINMP-ES-024203 B-10 IS1 F1.20 1 E41 -HPCIH-13A RESTRAINT AUG 2 E41 OWN PRE FA HI 1 E41-HPCIH-14 B-10 IS1 F1.20 1 E41-HPCIH-14 SPRING AUG 2 E41 OWN PRE FA HI 1 E41-HPCIH-15 0-1 0 IS1 F1.20 1 E41-HPCIH-15 RESTRAINT AUG 2 E41 OWN PRE FA HI 1 E41-HPCIH-16 ISllVTINMP-ES-024203 8-1 2 IS1 F1.20 1 E41-HPCIH-16 HANGER AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-17 8-1 2 IS1 F1.20 1 E41-HPCIH-17 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1E41-HPCIH-2 B-13A IS1 F1.20 1 E41-HPCIH-2 RESTRAINT AUG 2 E41 OWN PRE F-A H1 1 E41-HPCIH-22 B-1 1 IS1 F1.20 1 E41-HPCIH-22 RESTRAINT AUG 2 E41 OWN PRE FA HI 1 E41-HPCIH-23 B-1 1 IS1 F1.20 1 E41 -HPCIH-23 RESTRAINT AUG 2 E41 OWN PRE Page 20 - 36 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case FA HI 1 E41-HPCIH-24 B-1 1 IS1 F1.20 1 E41 -HPCIH-24 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1E41-HPCIH-25 B-1 1 IS1 F1.20 1 E41 -HPCIH-25 RESTRAINT AUG 2 E41 OWN PRE FA HI 1 E41-HPCIH-26 B-11 IS1 F1.20 1 E41 -HPCIH-26 RESTRAINT AUG 2 E41 OWN PRE FA HI 1 E41-HPCIH-27 B-1 1 IS1 F1.20 1 E41 -HPCIH-27 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1 E41 -HPCIH-27A B-I I IS1 F1.20 1 E41 -HPCIH-27A RESTRAINT AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-28 B-1 1 IS1 F1.20 1 E41 -HPCIH-28 ANCHOR AUG 2 E41 OWN PRE FA HI 1 E41-HPCIH-2A B-13A IS1 F1.20 1 E41 -HPCIH-2A RESTRAINT AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-3 B-13A IS1 F1.20 1 E41 -HPCIH-3 HANGER AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-38 B-1 1 IS1 F1.20 1 E41 -HPCIH-38 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-4 ISINTI B-13A IS1 F1.20 1 E41 -HPCIH-4 RESTRAINT AUG 2 E41 OWN PRE Page 21 - 36 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F-A HI 1E41-HPCIH-5 B-13A IS1 F1 20 1 E41 -HPCIH-5 RESTRAINT AUG 2 E41 OWN PRE F-A HI 1E41-HPCIH-6 6-1 3A IS1 F1.20 1 E41 -HPCIH-6 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1E41-HPCIH-7 8-1 3A IS1 F1.20 1 E41 -HPCIH-7 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-701 B-10 IS1 F1.20 1 E41 -HPCIH-701 SPRING AUG 2 E41 OWN PRE F -A H1 1 E41 -HPCIH-8 8-1 3 IS1 F1.20 1 E41 -HPCIH-8 SUPPORT AUG 2 E41 OWN PRE F-A HI 1 E41 -HPCIH-800 B-1 1 IS1 F1.20 1 E41-HPCIH-800 RESTRAINT AUG 2 E41 OWN PRE F-A HI 1 E41-HPSEH-10 8-1 5 IS1 F1.20 1 E41-HPSEH-10 SPRING AUG 2 E41 OWN PRE F -A HI 1 E41-HPSEH-14 8-1 6 IS1 F1.20 1 E41-HPSEH-14 HANGER AUG 2 E41 OWN PRE F-A HI 1 E41-HPSEH-15 B-16 IS1 F1.20 1 E41-HPSEH-15 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1E41-HPSEH-19 8-22 IS1 F1.20 1 E41 -HPSEH-19 HANGER AUG 2 E41 OWN PRE Page 22 - 36 Period 1 Period 2 112612006 1 Period 3

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1 HNP-I Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Category, Iso No. IternNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope I Method 1 Procedure Code Case F-A HI 1 E41-HPSEH-48 8-73 IS1 F1.20 1 E41-HPSEH-48 ANCHOR AUG 2 E41 OWN PRE FA H1 1E41-HPSEH-49 8-73 IS1 F1.20 1 E41 -HPSEH-49 HANGER AUG 2 E41 OWN PRE F -A HI 1E41-HPSEH-5 8-1 5 IS1 F1.20 1 E41 -HPSEH-5 RESTRAINT AUG 2 E41 OWN PRE F-A Hi 1 E41-HPSEH-50 8-73 IS1 F1.20 1 E41-HPSEH-50 HANGER AUG 2 E41 OWN PRE F -A HI 1E41-HPSEH-51 8-73 IS1 F1.20 1 E41 -HPSEH-51 HANGER AUG 2 E41 OWN PRE FA HI 1 E41-HPSEH-54 8-20 IS1 F1.20 1 E41 -HPSEH-54 SPRING AUG 2 E41 OWN PRE F -A HI 1 E41-HPSEH-56 8-1 9 IS1 F1.20 1 E41 -HPSEH-56 RESTRAINT AUG 2 E41 OWN PRE F-A HI 1 E41-HPSEH-59 8-1 9 IS1 F1.20 1 E41-HPSEH-59 RESTRAINT AUG 2 E41 OWN PRE F -A HI 1 E41-HPSEH-6 8-1 5 IS1 F1.20 1 E41-HPSEH-6 RESTRAINT AUG 2 E41 OWN PRE F -A H1 1 E41-HPSEH-60 8-1 9 IS1 F1.20 1 E41-HPSEH-60 RIGID SUPPORT AUG 2 E41 OWN PRE Page 25 - 36 Period 1 Period 2 112612006 1 Period 3

Revision:

1 Category, ItemNO, HNP-I Fourth Interval Class 2 Supports Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case FA HI 1 E41-HPSEH-71 8-73 IS1 F1.20 1 E41 -HPSEH-71 SPRING AUG 2 E41 OWN PRE FA HI 1 E41-HPSEH-74 8-73 IS1 F1.20 1 E41 -HPSEH-74 RIGID SUPPORT AUG 2 E4 1 OWN PRE FA HI 1 E41-HPSEH-75 lSlI1 6-73 IS1 F1.20 1 E41 -HPSEH-75 RESTRAINT AUG 2 E4 1 OWN PRE FA HI 1E41-HPSEH-78 8-73 IS1 F1.20 1 E41 -HPSEH-78 SPRING AUG 2 E4 1 OWN PRE F-A HI 1E41-HPSEH-79 B-69 IS1 F1.20 1 E41 -HPSEH-79 SPRING AUG 2 E4 1 OWN PRE F -A HI 1E41-HPSEH-810 8-73 IS1 F1.20 1 E41 -HPSEH-810 HANGER AUG 2 E4 1 OWN PRE FA HI 1E41-HPSEH-813 lSlI1 8-21 IS1 F1.20 1 E41 -HPSEH-813 SPRING AUG 2 E4 1 OWN PRE FA HI 1 E41-HPSEH-86 8-69 IS1 F1.20 1 E41 -HPSEH-86 SPRING AUG 2 E4 1 OWN PRE FA HI 1 E41-HPSEH-8A 8-1 5 IS1 F1.20 1 E41 -HPSEH-8A RESTRAINT AUG 2 E41 OWN PRE F -A HI 1 E41-HPSEH-9 8-1 5 IS1 F1.20 1 E41 -HPSEH-9 RESTRAINT AUG 2 E4 1 OWN PRE Page 27 - 36 Period 1 Period 2 Period 3

Revision:

1 HNP-1 Fourth Interval Class 2 Supports Plan Page 29 - 36 Southern Nuclear Operating Company Period 1 Period 2 PRE - - - - F -A HI 1 N11-MSH-13 8-77 IS1 ---- F1.20 I NI 1 -MSH-13 RESTRAINT AUG - - - - 2 N11 OWN ---- PRE - - - - F -A HI IN1 1-MSH-15 8-77 IS1 - - - - F1.20 1 N11 -MSH-15 RESTRAINT AUG - - - - 2 N11 OWN ---- PRE F -A HI 1 N11-MSH-11 8-77 IS1 F1.20 1 N11-MSH-11 RESTRAINT AUG 2 N11 OWN PRE F -A HI 1 N11-MSH-12 8-77 IS1 F1.20 1 N11 -MSH-12 RESTRAINT AUG F1.20 1 N11-MSH-16 HANGER AUG 2 N11 OWN PRE F -A H1 IN1 1-MSH-18 8-74 IS1 F1.20 1 N11-MSH-18 SPRING AUG 2 N11 OWN d V, 2 L? F rl -------- -------- ------- -------- -------- -------- ------- -------- s--- -------- Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A HI 1N11-AD-1 8-77 IS1 F1.20 1 N11 -AD-1 ANCHOR AUG 2 N11 OWN PRE F -A HI 1 N11 -MSH-1 8-76 IS1 F 1.20 1 N11 -MSH-1 SPRING AUG 2 N11 OWN PRE F -A HI 1N11-MSH-10 8-77 IS1 F1.20 1 N11 -MSH-10 SPRING AUG - - - - ---- - - - - - - - - - - - - ---- - - - - HANGER C9 2 2 5 5 ---- 2 N11 OWN ---- AUG - - - - OWN - - - - PRE - - - - 2 N11 OWN Period 3 - - - - - - - -

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Revision:

1 HNP-1 Fourth Interval Class 2 Snubber Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F-A H1 1 El 1-RHRH-316 8-37 IS1 F1.20S 1 El 1 -RHRH-316 MECH SNUBBER AUG 2 El 1 OWN PRE F -A HI 1El1-RHRH-319A ISIII B-50 IS1 F1.20S 1 El 1-RHRH-319A HYDR SNUBBER AUG 2 El 1 OWN PRE F -A HI 1 El 1 -RHRH-323A&B 8-36 IS1 F1.20S 1 El 1 -RHRH-323A&B HYDR SNUBBER AUG 2 El 1 OWN PRE F -A HI 1E11-RHRH-324 8-38 IS1 F1.20S 1 El 1 -RHRH-324 HYDR SNUBBER AUG 2 El 1 OWN PRE F -A HI lEl1-RHRH-325 8-38 IS1 F1.20S 1 El 1 -RHRH-325 MECH SNUBBER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-34 8-58 IS1 F1.20S 1 El 1 -RHRH-34 MECH SNUBBER AU G 2 El 1 OWN PRE FA HI 1 El 1 -RHRH-43 8-47 IS1 F1.20S 1 El l-RHRH-43 MECH SNUBBER AUG 2 El 1 OWN PRE F -A HI 1El1-RHRH-708A&B 8-52 IS1 F1.20S 1 El 1 -RHRH-708A&B MECH SNUBBER AUG 2 El 1 OWN PRE F-A H1 1 El 1 -RHRH-709 8-36 IS1 F1.20S 1 El 1 -RHRH-709 HYDR SNUBBER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-711 8-36 IS1 F1 20s 1 El 1-RHRH-711 HYDRSNUBBER AUG 2 El 1 OWN PRE Period 1 Period 2 Period 3 Revision:

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

Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A HI 1E11-RHRH-713 8-42 IS1 MECH SNUBBER AUG OWN PRE F-A HI 1 El 1-RHRH-716 8-42 IS1 F1.20S 1 El 1-RHRH-716 MECH SNUBBER AUG 2 El 1 OWN PRE F -A HI 1 El 1-RHRH-719A&B 8-37 IS1 F1.205 1 El 1-RHRH-719A&B HYDR SNUBBER AUG 2 El 1 OWN PRE F -A H1 1 El 1-RHRH-722 8-51 IS1 F1.20S 1 El 1 -RHRH-722 HYDRSNUBBER AUG 2 El 1 OWN PRE F -A HI 1El1-RHRH-725 8-20 IS1 F1.20S 1 El 1 -RHRH-725 MECH SNUBBER AUG 2 El 1 OWN PRE FA HI 1 E21-CSH-57 ISlll 8-7 IS1 F1.20S 1 E21 -CSH-57 HYDR SNUBBER AUG 2 E21 OWN PRE F -A HI 1E21-CSH-71 8-3 IS1 F1.20S 1 E21 -CSH-71 HYDRSNUBBER AUG 2 E2 I OWN PRE F -A HI 1 E21-CSH-79 B-6 IS1 F1.205 1 E21 -CSH-79 HYDR SNUBBER AUG 2 E21 OWN PRE F-A HI 1E41-HPCIH-13 B-10 IS1 F1.205 1 E41 -HPCIH-13 HYDRSNUBBER AUG 2 E41 OWN PRE F -A HI 1 E41-HPCIH-700 8-1 3 IS1 F1.205 1 E41 -HPCIH-700 SNUBBER AUG 2 E41 OWN PRE Period 1 Period 2 Period 3

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1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Category, lso No. ItemNO, Comp. Desc.

class Summary I ComplD I System Scope I Method I Procedure Code Case F -A HI 1821-H822 C-81 IS1 F1.30 1 821-H822 SPRING AUG 3 821 OWN PRE F -A HI 1821 -H824 ISIII C-83 IS1 F1.30 1 821 -H824 SPRING AUG 3 821 OWN PRE F -A H1 1 821 -H-825 C-88 IS1 F1.30 1821 -H-825 RESTRAINT AUG 3 821 OWN PRE F -A HI 1821-H826 C-86 IS1 F1.30 1 821 -H826 RESTRAINT AUG 3 821 OWN PRE F -A HI 1 B21 -MVVH-3 ISllVTINMP-ES-024201 C-80 IS\ F1.30 1 B21 -MVVH-3 SPRING AUG 3 821 OWN PRE FA HI 1821 -MVVH-30 C-91 IS1 F1.30 1821 -MWH-30 SPRING AUG 3 821 OWN PRE F -A HI 1821 -MVVH-34 C-91 IS1 F1.30 1821 -MVVH-34 SPRING AUG 3 821 OWN PRE F -A HI 1821 -MVVH-700 C-82 IS1 F1.30 1821-MWH-700 RESTRAINT AUG 3 821 OWN PRE F -A HI 1821 -MVVH-701 C-80 IS1 F1.30 1821 -MVVH-701 RESTRAINT AUG 3 821 OWN PRE FA H1 1 821 -MVVH-702 C-84 IS[ F1.30 1821 -MVVH-702 RESTRAINT AUG 3 821 OWN PRE Page 2 - 25 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Page 3 - 25 1126l2006 1 Period 1 Period 2 Period 3 1 821 -MVVH-703 RESTRAINT AUG 1- - - - - F1.30 (Or- 2 2 5 5 F1.30 1 821 -R1 RESTRAINT AUG - - - - 3 82 1 OWN - - - - PRE - - - - FA H1 1821-R2 C-89,-90 IS1 - - - - F1.30 1 821 -R2 RESTRAINT AUG - - - - 5; 5 5 ------------

Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method I Procedure Code Case FA H1 1821-MVVH-703 C-92 IS1 PRE F -A HI 1821 -MVVH-8 C-85 IS1 F1.30 1 821 -MVVH-8 SPRING AUG 3 821 OWN PRE F -A HI 1821-MVVH-9 C-87 IS1 F1.30 1 821 -MWH-9 SPRING AUG e3 2 2 ,I I- PRE 1- - - - F-A H1 1 821 -R7 C-80 IS1 ---- - - - - - - - - - - - - - - - - - - - - 3 821 OWN PRE F -A HI 1821 -R3 C-78,-89 IS1 F1.30 1 821 -R3 RESTRAINT AUG 3 821 OWN PRE F -A HI 1821-R4 C-78,-79 IS1 F1.30 1 821 -R4 RESTRAINT AUG F1.30 1621 -R7 RESTRAINT AUG - - - - 3 821 OWN ---- PRE - - - - F-A HI 1821 -R7-R8 C-83 IS1 ---- F1.30 1821 -R7-R8 RESTRAINT AUG - - - - - - - - ------------ - - - - - - - - - - - - ________---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 3 821 OWN PRE F -A HI 1821-R8 C-81 IS1 F1.30 1 821 -R8 RESTRAINT AUG 3 621 OWN PRE - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - -------- ----S--- -------- - - - - . - - -

Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Page 4 - 25 Southern Nuclear Operating Company Period 1 Period 2 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case FA HI 1821 -SS-H700 C-85 IS1 F1.30 1 B21 -SS-H700 RESTRAINT AUG 3 82 1 OWN PRE FA H1 1 B21 -SS-H701 C-86 IS1 F1.30 1 B21 -SS-H701 RESTRAINT AU G 3 821 OWN PRE FA H1 1 B21 -SS-H702 C-88 IS1 F1.30 1 B21 -SS-H702 RESTRAINT AU G 3 821 OWN PRE FA HI 1821-SS-H703 C-88 IS1 F1.30 1 B21 -SS-H703 RESTRAINT AU G 3 82 1 OWN PRE F -A HI 1E11-ISH-1 C-3 IS1 F1.30 1E11-ISH-1 SUPPORT AU G 3 El 1 OWN PRE F -A HI 1El1-ISH-10 C-2 IS1 F1.30 1 El 1-ISH-10 HANGER AU G 3 El 1 OWN PRE F -A HI 1E11-ISH-11 C-2 IS1 F1.30 1 El 1 -ISH-11 RESTRAINT AUG 3 El 1 OWN PRE F -A H1 1 El 1-ISH-12 C-2 IS1 F1.30 1El1-ISH-12 RESTRAINT AUG 3 El 1 OWN PRE F -A HI 1 El 1 -ISH-13 C-2 IS1 F1.30 1 El 1-ISH-13 RESTRAINT AUG 3 El 1 OWN PRE F -A HI 1E11-ISH-15 C-3 IS1 F1.30 1 El 1 -ISH-15 SUPPORT AU G 3 El 1 OWN PRE 112612006 I Period 3 D h 2 2 C 5 ---- ---- ---- ---- ---- ---- ---- ---- - - - - ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- ---- - - - - ---- ----

Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A H1 1 El 1-ISH-704 C-4 IS1 F1.30 1 El l-ISH-704 RESTRAINT AUG 3 El 1 OWN PRE F -A H1 1Ell-ISH-8 C-2 IS1 F1.30 1 El 1-ISH-8 RESTRAINT AUG 3 El 1 OWN PRE F -A HI 1 El 1-ISH-84 C-2 IS1 F1.30 1 El I -1SH-84 RESTRAINT AUG 3 El I OWN PRE F -A H1 1 El 1-ISH-85 C-4 IS1 F1.30 1 Ell-ISH-85 ANCHOR AUG 3 El 1 OWN PRE F -A H1 1 El I-ISH-9 C-2 IS1 F1.30 1 E11-ISH-9 RESTRAINT AUG 3 El I OWN PRE F -A H1 1E11-RHRH-100 C-7 IS1 F1.30 1E11-RHRH-100 HANGER AUG 3 El 1 OWN PRE F -A H1 1 El 1-RHRH-101 C-7 IS1 F1.30 1 El 1-RHRH-101 HANGER AUG 3 El 1 OWN PRE F -A H1 1 El 1-RHRH-102 C-5 IS1 F1.30 1 El 1-RHRH-102 HANGER AUG 3 El 1 OWN PRE F -A H1 1 El 1-RHRH-103 C-6 IS1 F1.30 1 El 1 -RHRH-103 HANGER AUG 3 El 1 OWN PRE F -A H1 1 El 1-RHRH-104 C-6 IS1 F1.30 1 El 1 -RHRH-104 RESTRAINT AUG 3 El I 0 WN PRE Page 7 - 25 Period 1 Period 2 Period 3

Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case FA H1 1 El 1-RHRH-115 C-7 IS1 F1.30 1 E11-RHRH-115 RESTRAINT AUG 3 El 1 OWN PRE FA HI 1El l-RHRH-278 C-5 IS1 F1.30 1 El 1 -RHRH-278 RESTRAINT AUG 3 El 1 OWN PRE FA H1 1 El 1-RHRH-281 C-5 IS1 F1.30 1 Ell-RHRH-281 ANCHOR AUG 3 El 1 OWN PRE FA H1 1E11-RHRH-283 C-5 IS1 F1.30 1 El 1 -RHRH-283 RESTRAINT AUG 3 El 1 OWN PRE F-A HI 1E11-RHRH-285 C-5 IS1 F1.30 1 El 1 -RHRH-285 RESTRAINT AUG 3 El 1 OWN PRE FA H1 1 El l-RHRH-287 C-5 IS1 F1.30 1 El l-RHRH-287 RESTRAINT AUG 3 El 1 OWN PRE FA H1 1 El 1-RHRH-290 C-7 IS1 F1.30 1 El 1 -RHRH-290 ANCHOR AUG 3 El 1 OWN PRE F-A H1 1 El 1-RHRH-291 C -7 IS1 F1.30 1 El 1 -RHRH-291 RESTRAINT AUG 3 El 1 OWN PRE F-A HI 1 El 1 -RHRH-293 C-7 IS1 F1.30 1 El 1 -RHRH-293 RESTRAINT AUG 3 El 1 OWN PRE F -A H1 1 El 1-RHRH-295 C -7 IS1 F1.30 1Ell-RHRH-295 RESTRAINT AUG 3 El 1 OWN PRE Page 9 - 25 Period 1 Period 2 Period 3

Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case FA HI 1 El I-RHRH-59 C-5 IS1 F1.30 1 El 1 -RHRH-59 HANGER AUG 3 El I OWN PRE FA HI 1 El I-RHRH-65 C-6 IS1 F1.30 1 El 1 -RHRH-65 HANGER AUG 3 El I OWN PRE F-A HI 1 El 1-RHRH-801A C-5 IS1 F1.30 1 El 1 -RHRH-801A ANCHOR AUG 3 El I OWN PRF . ,,- F-A HI I El I-RHRH-90 C -5 IS1 RESTRAINT AUG OWN PRE F-A HI 1 El 1-RHRH-91 C-5 IS1 HANGER AUG OWN PRF . ,.- F-A HI I El I-RHRH-92 C-5 IS1 F1.30 1 El 1 -RHRH-92 HANGER AUG 3 El I OWN PRE FA HI 1E11-RHRH-93 C-5 IS1 F1.30 1 El 1-RHRH-93 HANGER AUG 3 El 1 OWN PRF . . .- F-A HI I El I-RHRH-94 C-5 IS1 RESTRAINT AUG OWN PRE F-A HI 1 El I-RHRH-95 C-5 IS1 SPRING AUG OWN PRE FA HI 1 El 1-RHRH-96 C-7 IS1 SPRING AUG OWN PRE Page 11 - 25 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case FA HI 1E11-RHRH-97 C-7 IS1 F1.30 1 El 1-RHRH-97 HANGER AUG 3 El 1 OWN PRE F -A H1 1 El 1-RHRH-98 C-7 IS1 F1.30 1 El 1 -RHRH-98 HANGER AUG 3 El 1 OWN PRE F -A HI 1 El 1-RHRH-99 ISIII C-7 IS1 F1.30 1 El 1-RHRH-99 HANGER AUG 3 El 1 OWN PRE F -A HI 1 E51 -RCICH-1 C-948 IS1 F1.30 1 E51-RCICH-1 RESTRAINT AUG 3 E5 1 OWN PRE F -A HI 1 E51-RCICH-10 C-94A IS1 F1.30 1 E51-RCICH-10 RESTRAINT AUG 3 E5 1 OWN PRE F -A HI 1 E51-RCICH-11 ISIIVTI C-94A IS1 F1.30 1 E51-RCICH-11 RESTRAINT AUG 3 E51 OWN PRE F -A HI 1 E51-RCICH-12 C-94A IS1 F1.30 1 E51 -RCICH-12 RESTRAINT AUG 3 E5 1 OWN PRE FA HI 1E51-RCICH-13 C-94A IS1 F1.30 1 E51-RCICH-13 RESTRAINT AUG 3 E5 1 OWN PRE FA HI 1 E51-RCICH-14 C-94A IS1 F1.30 1 E51-RCICH-14 RESTRAINT AUG 3 E5 1 OWN PRE FA Hl 1E51-RCICH-15 C-94A IS1 F1.30 1 E51-RCICH-15 RESTRAINT AUG 3 E5 1 OWN PRE Page 12 - 25 Period 1 Period 2 Period 3 LZUHC ' 9ZUHC ' SZUHC PZtlHC EZUHC ' eZZUHC - u $ al al UI a $g? noo 2 ?! 3 2 0" L n - '0 0 5 2 - 01 P 0 L) U) E d ZI U) - 9 B i O, T Ev 3 - U) 2 C6 02 3 SE, < d2~ - - -2s: !don I- 2 a 3 I- ra > a n ; 0, J? S = $2 o a !? L m-. E e Z 0 0 5, LLLO azlL j3 3u -<on I- z a a c I- 5 : > a D i 1 Y' 5 I $ 0 - 0 D K !? I In 7 -wm s.-W 0 f. 2 LLLO -22% !<on I- z a , E e ., 8 W 1 a . t: -'$ 3 = q 0 - 0 0 a !? I -zz II-w 0 5 2 LLLO azw j33E <On I- z a K c I- :: 1 a 0 i j '? 5 $ c - 0 0 a U ' m - EE2 0 f. '2 LLLO (3ZW -33u !a o a I- z a K 1 I- !: > K ; j ?J 2 5 : 0 7 9: ! - -zz K.-W 0 5'2 LLLO Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Page 14 - 25 Period 1 Period 2 112612006 I Period 3 V) 2 2 5 5 - -------- - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case F -A HI 1 E51 -RCICH-801 C-94A IS1 F1.30 1 E51 -RCICH-801 ANCHOR AUG 3 E51 OWN PRE F -A H1 1 E51-RCICH-802 C-94B IS1 F1.30 1 E51 -RCICH-802 ANCHOR AUG 3 E51 OWN e3 2 2 5 5 ------- - - - - PRE F-A H1 1 E51-RCICH-9 C-94A IS1 F1.30 1 ES1-RCICH-9 RESTRAINT AUG 3 E5 1 OWN - - - - - - - - - - - - PRE F-A HI 1P41-ISH-25 C-8 IS1 F1.30 1 P41 -ISH-25 RESTRAINT AUG 3 P41 OWN - - - - - - - - - - - - PRE F-A HI 1P41-ISH-26 ISlll C-8 IS1 F1.30 1 P41 -ISH-26 SUPPORT AUG 3 P41 OWN - - - - ------------ - - - - - - - - - - - - - - - - - - - - PRE F-A H1 1 P41 -ISH-27 C-10 IS1 F1.30 1 P41 -ISH-27 RESTRAINT AUG 3 P41 om - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - PRE F-A H1 1 P41 -ISH-28 C-1 0 IS1 F1.30 1 P41 -ISH-28 SUPPORT AUG 3 P41 om PRE - - - - - - - - I - - - - F-A H1 1 P41 -ISH-30 C-9 IS1 ------------ - - - - - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - PRE F-A H1 1 P41-ISH-29 C-9 I SI F1.30 1 P41 -ISH-29 SUPPORT AUG 3 P41 om SUPPORT - - - - - - - - - - - - - - - - -s---------- - - - - - - - - - - - - - - - - - - - - AUG ---- - - - - - - - - - - - - - - - - ----..------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - PRE FA HI 1 P41-ISH-31 C-1 1 IS1 F1.30 1 P41-ISH-31 SUPPORT AUG 3 P41 om PRE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----s----.-- - - - . - . - - . - . - - . - . - - - - - - - - - - - -

Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD I System Scope I Method I Procedure Code Case F -A H1 1 P41 -ISH-33 C-8 IS1 F1.30 1 P41 -ISH-33 RESTRAINT AUG 3 P41 OWN Page 15 - 25 Period 1 Period 2 1'2612006 I Period 3 PRE - - - - I - - - - - - F-A H1 1 P41 -ISH-34 C-1 1 IS1 ------------

SUPPORT AUG ---- OWN RESTRAINT AUG ...... OWN ----I----

ANCHOR AUG ..... OWN ----I----

ANCHOR AUG --- ... OWN PRE - - - - F -A H1 1 P41 -1SH-67 C-10 IS1 - - - - SUPPORT PRE I- - - - F -A H1 1 P41-ISH-68 ISIII C-10 IS1 ---- SUPPORT SUPPORT PRE I- - - - F-A H1 1 P41-ISH-70 C-8 IS1 ---- SUPPORT PRE - - - - F -A H1 1 P41 -ISH-700 C-1 1 IS1 ---- RESTRAINT AUG - - - - OWN ---- PRE - - - -

Period 3 Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Page 18 - 25 Period 2 5 $ 5 5 S-- - - - - - - - - - - - - - - - - -------- - - - - - - - - -------- - - - - - - - - - - - - -------- -------- - - - - - - - - - - - - - - - - - - - - - - - - - -------- -------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - -------- -------- ---- . - - - . - - - -I- - - - Southern Nuclear Operating Company Category, Iso No. ItemNO, Cornp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A HI 1P41-SDGH-3 C-19 IS1 F1.30 1 P41-SDGH-3 RESTRAINT AUG 3 P4 1 om PRE FA HI 1 P41-SDGH-31 C-20 IS1 F1.30 1 P41 -SDGH-31 RESTRAINT AUG 3 P41 om pRE F -A H1 1 P41-SDGH-4 C-18 IS1 F1.30 1 P41 -SDGH-4 SPRING AUG 3 P41 om PRE F-A HI 1 P41 -SDGH-41 C-20 IS1 F1.30 1 P41 -SDGH-41 RESTRAINT AUG 3 P41 om PRE F -A HI 1 P41 -SDGH-46 C-I 7 IS1 F1.30 1 P41-SDGH-46 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41-SDGH-47 C-17 IS1 F1.30 1 P41 -SDGH-47 RESTRAINT AUG 3 P41 om PRE FA HI 1 P41-SDGH-48 C-17 IS1 F1.30 1 P41 -SDGH-48 RESTRAINT AUG 3 P41 om PRE F -A HI 1 P41 -SDGH-49 C-17 IS1 F1.30 1 P41 -SDGH-49 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41-SDGH-5 C-18 IS1 F1.30 1 P41 -SDGH-5 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41-SDGH-50 C-17 IS1 F1.30 1 P41 -SDGH-50 RESTRAINT AUG 3 P41 PRE OWN Period 1 A c.3 2 2 5 5 ----- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - I- - -

Revision:

1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD 1 System Scope I Method I Procedure Code Case F-A H1 1 P41 -SDGH-51 C-19 IS1 F1.30 1 P41 -SDGH-51 RESTRAINT AUG 3 P41 OWN PRE F-A HI 1 P41-SDGH-6 C-18 IS1 F1.30 1 P41 -SDGH-6 RESTRAINT AUG 3 P41 OWN PRE F -A H1 1 P41 -SDGH-7 C-18 IS1 F1.30 1 P41 -SDGH-7 SPRING AUG 3 P41 OWN PRE F-A H1 1 P41-SDGH-700 C-20 IS1 F1.30 1 P41 -SDGH-700 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41-SDGH-701 C-20 IS1 F1.30 1 P41-SDGH-701 RESTRAINT AUG 3 P 41 OWN PRE FA H1 1 P41-SDGH-703 IS111 C-18 IS1 F1.30 1 P41-SDGH-703 ANCHOR AUG 3 P41 OWN PRE FA H1 1 P41 -SDGH-800 C-18 IS1 F1.30 1 P41 -SDGH-800 RESTRAINT AUG 3 P41 OWN PRE F-A H1 1 P41-SDGH-A1 C-19 IS1 F1.30 1 P41 -SDGH-A1 Anchor at Floor AUG 3 P41 OWN PRE F-A HI 1 P41 -SWH-1 C-36 IS1 F1.30 1 P41 -SWH-1 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41 -SWH-10 C-73 IS1 F1.30 1 P41 -SW-10 RESTRAINT AUG 3 P41 OWN PRE Page 19 - 25 1126'2006 1 Period 1 Period 2 Period 3

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1 HNP-1 Fourth Interval Class 3 Supports Plan Southern Nuclear Operating Company Category, Iso No. IternNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case F -A HI 1 P41 -SWH-236 C-37A IS1 F1.30 1 P41 -SWH-236 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41-SWH-237 C-37A IS1 F1.30 1 P41 -SW-237 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41 -SWH-260 C-120 IS1 F1.30 1 P41 -SWH-260 AUG 3 P41 OWN PRE F -A HI 1 P41 -SWH-269 C-39 IS1 F1.30 1 P41 -SWH-269 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41 -SWH-274 C-22 IS1 F1.30 1 P41 -SWH-274 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41 -SWH-275 C-22 IS1 F1.30 1 P41 -SWH-275 RESTRAINT AUG 3 P41 OWN PRE F -A H1 1 P41 -SWH-276 C-38 IS1 F1.30 1 P41 -SWH-276 RESTRAINT AUG 3 P41 OWN PRE F -A HI 1 P41 -SWH-290 C-36 IS1 F1.30 1 P41 -SWH-290 ANCHOR AUG 3 P41 OWN PRE F -A HI 1 P41 -SWH-3 C-39 IS1 F1.30 1 P41 -SWH-3 HANGER AUG 3 P41 OWN PRE F -A H1 1 P41 -SWH-4 C-39 IS1 RESTRAINT AUG OWN PRE Page 23 - 25 Period 1 Period 2 Period 3

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1 HNP-1 Fourth Interval Class 3 Snubber Plan Southern Nuclear Operating Company Page 4 - 4 112612006

/ Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope I Method I Procedure Code Case F -A HI 1B21-SS-9 C-81 IS1 F1.30S 1 821 -SS-9 MECH SNUBBER AUG 3 82 1 ow PRE FA HI 1 El 1-RHRH-282 ISlIl C -5 IS1 F1.30S 1 El 1-RHRH-282 HYDR SNUBBER AUG 3 El 1 OWN PRE FA HI 1 El 1-RHRH-286 C-5 IS1 F1.30S 1 El 1-RHRH-286 HYDRSNUBBER AUG 3 El 1 ow PRE F -A H1 1 El 1-RHRH-292 ISIII C-7 IS1 F1.30S 1 El 1-RHRH-292 HYDRSNUBBER AUG 3 El 1 ow PRE F -A HI 1 El 1-RHRH-299 C-7 IS1 F1.30S 1 El 1 -RHRH-299 HYDR SNUBBER AUG 3 El 1 ow PRE FA HI 1E11-RHRH-344 C -6 IS1 F1.30S 1 El 1-RHRH-344 MECH SNUBBER AUG 3 El 1 ow PRE F -A H1 1E11-RHRH-348A&B C-6 IS1 F1.30S 1 El 1-RHRH-348A&B HYDRSNUBBER AUG 3 El 1 ow PRE I - - - - I - - - - - - d Y) 2 2 5 5 ------------ - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - - - - - - s - - - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - A '-, 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - w r- 2 2 5 5 - - - - - - - - - - - - s--- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

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1 HNP-1 Fourth Interval Equipment Supports Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case F -A HI 1 E41 -COO1 -SO1 1 E41 -SK7 IS1 F1.40 1 E41 -COO1 401 PUMP AUG 2 E41 OWN PRE F -A HI 1 E51-C001-SO1 1 E51 -SK8 IS1 F1.40 1 E51 -COO1 -SO1 PUMP AUG 2 E51 OWN PRE F -A HI 1 P41 -C001A-SO1 1 P41 -SKI 4 IS1 F1.40 1 P41 -C001A-SO1 PUMP AUG 3 P41 OWN PRE F -A HI 1 P41-C001A-SO2 ISIIVTINM P-ES-024-203 1 P41 -SKI 4 IS1 F1.40 1 P41 -COO1 A-SO2 PUMP AUG 3 P41 OWN PRE F -A HI 1 P41-COO1 &SO1 1 P41 -SKI 4 IS1 F1.40 1 P41 -COO1 0-SO1 PUMP AUG 3 P41 OWN PRE FA HI 1 P41 -COO1 0-SO2 1 P41 -SKI 4 IS1 F1.40 1 P41 -COO1 0402 PUMP AUG 3 P41 OWN PRE F -A HI 1 P41-COO1 C-SO1 1 P41 -SKI 4 IS1 F1.40 1 P41 -COO1 C-SO1 PUMP AUG 3 P41 OWN PRE F -A HI 1 P41 -COO1 C-SO2 1 P41 -SKI 4 IS1 F1.40 1 P41 -COO1 C-SO2 PUMP AUG 3 P41 OWN PRE F-A HI 1 P41 -COO1 D-SO1 1 P41 -SKI 4 IS1 F1.40 1 P41 -COO1 D-SO1 PUMP AUG 3 P41 OWN PRE F -A HI 1 P41 -COO1 D-SO2 1 P41 -SKI4 IS1 F1.40 1 P41 -COO1 D-SO2 PUMP AUG 3 P41 OWN PRE Page 4 - 6 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval Equipment Supports Plan Southern Nuclear Operating Company category, ISO NO. IternNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case F-A H1 1 P41 -Dl 03A-SO1 1 P41 -SKI 5 IS1 F1.40 1 P41 -Dl 03A-SO1 STRAINER AUG 3 P41 OWN PRE F -A HI 1 P41-D103B-SO1 1 P41 -SKI 5 IS1 F1.40 1 P41 -D103B-SO1 STRAINER AUG 3 P41 OWN PRE . ~- F -A H1 1 T41-B002A-SO1 1 T41 -SKI 6 IS1 F1.40 1 T41 -BOON-SO1 RHR & CS PMP RM CLR AUG 3 T41 OWN PRE F -A H1 1 T41 -B002B-SO1 1 T41 -SKI6 IS1 F1.40 1 T41-80028-SO1 RHR & CS PMP RM CLR AUG 3 T41 OWN PRE F -A H1 1 T41-B003A-SO1 1 T41 -SKI6 IS1 F1.40 1 T41 -B003A-SO1 RHR & CS PMP RM CLR AUG 3 T4 1 OWN PRE F-A H1 IT41 -B003B-SO1 1 T41-SKI6 IS1 F1.40 1 T41 -B003B-SO1 RHR & CS PMP RM CLR AUG 3 T41 OWN PRE . . .- F -A H1 1 T41-B005A-SO1 1 T41 -SK17 IS1 F1.40 1 T41 -B005A-SO1 HPCl PMP RM CLR AUG 3 T41 OWN PRE F -A H1 1T41-B005B-SO1 1 T41 -SK17 IS1 F1.40 1 T41 -BOO5B-SO1 HPCl PMP RM CLR AUG 3 T41 OWN PRE F -A H1 1 T47-B007A-SO1 1 T47-SK09 IS1 F1.40 1 T47-B007A-SO1 COOLING UNIT AUG 2 T47 OWN PRE FA H1 1 T47-80078-SO1 1 T47-SK09 IS1 COOLING UNlT AUG OWN PRE Page 5 - 6 Period 1 Period 2 Period 3 88 8 8 LZHHC SZUHC SZHHC PZUHC CZUHC Pa 63 ma 8 8 8 8 a eZZ~HCnnasm<~8amo8mmnm k z 02 5'3 IIIIIIIIIIIIIIII IIIIJIIIIIIIIIII m"8!nn8tn8o 8m~ 8 1111111111111111

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LZHH1 SZHHC 9ZHH1 PZHHL EZHHL eZZWH1 u' WQ 8 8 D 8 9 b B 8 8 9 8 8 8 8 < 8 8 8 8 t 8 8 8 11,11111 IIIIIIII m 0 8 8 8 8 8 8 IIII!III IIIIISII m 8 I 8 8 6 8 8 ,,,,,I,, IIIIIIII 8 m t B m 8 I a - > k I w m 7 cn m rn $; m - -mm I-m ffl 0 F U e n - u 0 5 f - z 0 U V) f CI W > 9 P n 0 - mrn IY W m m 3 E s IY W m m 3 Z ffl -z.- a-mm w1-m s 0 FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 1 of 46 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. This document shows exams performed under NUREG-0313 and 3 rd Interval exams to satisfy BWRVIP-075. It also shows the 1 st outage of the 4 th Interval; but, the balance of the 4 th Interval exams are not shown. The remaining 4 th Interval exams (scheduled for later in the interval) will be scheduled after the results of the 1R22 outage have been evaluated.

Based on good 1R22 results (no indications) or bad results (crack-like indi cations), along with applicab le industry issues (if any), the remainder of the examinations will be scheduled appropriately.

BACKGROUND Due to extensive Intergranular Stress Corrosion Cracking (IGSCC), much of the stainless steel piping for the HNP-1 Recirculation System, the RHR System, and the RWCU System was overlayed with IGSCC resistant material during the mid-1980's. Each of the remaining welds (where the configurati on 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 whic h was subsequently superseded by Generic Letter 88-01 (GL 88-01), "NRC Position on Inte rgranular Stress Corrosion Cracking in BWR Austenitic Stainless Steel Piping" a nd NUREG-0313, "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping". Inspection Categories were established ba sed on GL 88-01/NUREG-0313 requirements.

GL 88-01/NUREG-0313 Cate gories currently appli cable to HNP-1 are:

Category A - Welds are made from materials that are resistant to IGSCC due to their metallurgical properties. GL 88-01/

NUREG-0313 specifies that 25% of the population be examined every 10 years.

Category C - Welds are made from material that is considered susceptible to IGSCC, but the propensity for IGSCC was mitigated by stress improvement after more than two cycles of operation. GL 88-01/NUREG-0313 specifies that the entire population be examined once every 10 years.

Category E - Welds that have been overlayed with IGSCC resistant material. GL 88-01/NUREG-0313 specifies that the entire population be examined every two refueling

outages.

However, 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 sizi ng of IGSCC, new inspection criteria were subsequently proposed in BWRVIP-075 (issu ed on October 27, 1999 for NRC review).

Table 1 lists key dates and actions associated with the transition from GL 88-01 to BWRVIP-075 requirements at HNP-1.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 2 of 46 Rev.1.0 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. 12/2006 NRC grants approval of ISI-ALT-3 to continue during the 4 th Interval with the alternatives originally set forth in RR-39.

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.

This bases document is based on the NRC's final Safety Evaluation for BWRVIP-075 dated May 14, 2002 with the draft version of BWRV IP-075-A used for clarification purposes.

The sample size required to be examined by BWRVIP-075 is smaller than that required by ASME Section XI. Therefore, Relief Request RR-39 for the 3 rd Interval (approved by the NRC) and ISI-ALT-3 for the 4 th Interval were submitted to the NRC. These requests allow the use of the new sample sizes specified in BWRVIP-075 as an alternative to 10 CFR 50.55a requirements for Category B-J and B-F welds.

Any examination performed during the 3 rd or 4 th Interval may be credited toward the percentage requirements as l ong as the VIP-75 pre-requisites were met, prior to the examination.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 3 of 46 Rev.1.0

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 19 Category A welds. There is an equivalent Item Number desi gnated as "Table 2" in the ScheduleWorks Tables with 19 welds.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 4 of 46 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.

CATEGORY A VIP-75 WELD SELECTION The new examination frequency for Category A welds is a function of their ASME Section XI Code classification, as follows:

B-F Scope (N/A to Hatch 1)

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 1 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.

The NRC Final SE dated May 14, 2002, concluded that in order to reduce the inspection sample size to less than 25 percent, the piping needs the application of two mitigation methods. The resistant material is one mitigating measure and processes such as IHSI, MSIP, Heat Sink Welding, or HWC are a second mitigating measure. In the response to this open item, by letter dated August 28, 2001, the BWRVIP c oncluded that, while they did not agree with the need to apply a second mitigator, they would agree with the staff position to resolve the open item. Therefore, welds with resistant material and an effective second mitigating measure are considered to have low likelihood of IGSCC initiation and a sample size of 10% may be used.

The scope consists of the RWCU welds s hown in Table 2 and are discussed below.

Table 2 Welds

Table 2 lists 19 ASME Category B-J, NUREG-0313 Category A RWCU welds that are all located in the RWCU discharge line. The scope of these welds extends from the branch connection on the 20" RHR line to the outboard RWCU isolation valves. [Welds downstream of the outboard containment isolati on valve are not considered in the GL 88-01 scope because modifications to the valves were made as part of Generic Letter 89-10 actions, to ensure that they can close against full reactor pressure differential pressure in the

unlikely event of a break downstream of the va lves]. Per the NRC Final SE dated May 14, FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 5 of 46 Rev.1.0 2002, a 25% sample of these welds may be examined every 10 years and if there is effective hydrogen water chemistry (HWC) may further reduce their Category B-J inspection frequency.

As described in Appendix B, HNP-1 has effective hydrogen water protection as measured at the bottom of the reactor. However, each pipe may see different degrees of protection due to its configuration, location, and service. For these 19 welds, noble metal is added periodically (with RWCU running) such that noble metal pl ates should plate out on each of the 19 welds. Additionally, HNP-1 continuously injects a reduced level of hydrogen with RWCU running; therefore, there should be effective HWC for each of these 19 welds and a 10% sample (or 2 welds) may be examined.

Welds in Table 2 are broken out for documentation purposes by their material type, as follows: (Note: Weld 1 and 9 were preemptively overlayed).

There are 13 welds (welds 2 thru 3, 6 thru 10A, 11 thru 13, and 17 thru 19) joining 316 Nuclear Grade (NG) stainless steel material to 316 NG material. Weld filler metal was 308L. Per the NRC Staff Position on Materials found in Generic Letter 88-01 these 14 welds are not considered to be susceptible to IGSCC (See Positions 1 and 2).

Additionally, each received an MSIP treatment and baseline examination in 1993. They were subsequently re-examined in 1994 and later.

There are 4 welds (welds 4, 5, 14, and 20) joining 316 NG material piping to IGSCC resistant cast stainless valves. Per the NRC Staff Position on Inspection Schedules found in Generic Letter 88-01 welds joining resistant material to pumps and valves will be considered to be resistant material and included in Category A. (See Position 2). Additionally, each received an MSIP treatment and baseline examination in 1993. They were subsequently re-examined in 1994 and later.

There are two welds located in containment penetration X-14 that are inaccessible for stress improvement purposes and are inaccessible for examination. They are weld

1G31-1RWCUM-6-D-15B which joins IGSCC resistant 304L piping to 304L piping and weld 1G31-1RWCUM-6-D-15C which join s the penetration flued head (that has corrosion resistant 308L cladding on the ID) to corrosion resistant 304L pipe. Per the NRC Staff Position on Materials found in Generic Letter 88-01 these welds are not considered to be susceptible to IGSCC. (See Position 3).

In order to use the 10% sample size, the two welds to be examined should be selected using risk insights. Per VIP-75, piping that performs an ECCS function, or performs a containment function and is lo cated between the drywell and the outboard isolation valve, should have higher priority for examination over that piping which functions only as the reactor coolant pressure boundary. During th e 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 attributes that would promote IGSCC should have higher priority for inspection. The attributes that may be FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 6 of 46 Rev.1.0 considered include: high carbon or low ferrite content, crevice or st agnant flow condition, evidence of weld repair, surface cold work, a nd high fit-up, residual and operating stresses.

None of the 19 welds have an ECCS func tion; however, RWCU welds 17, 18, 19, and 20 are located between the drywell and the outboard isolation valve.

In the report, "Weld Prioritization for Adopti on of BWRVIP-75 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, surface cold work, and high fit-up, residual and operating stresses. This prioritization is shown in column 4 (SIA Priority) of Table 2 and the highest priority welds are those with the lowest priority number.

As shown in Table 2, welds 4, 5, 14, and 20 were assigned a Priority 2, with the remainder assigned a Priority 4.

Welds 4, 5, and 14 were examined during 1R21 (2/2004), which exceeded the 10%

requirement for the 3 rd Interval.

Weld 20 which is the only weld which has bot h a high SIA Priority and is located between the drywell wall and the outboard containment isolation valve will be examined during 1R22 (2/2006) for 4 th Interval credit. Weld 4, 5, or 14 will be examined later in the 4 th Interval to complete the requirements.

CATEGORY A VIP-75 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 de tected, 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. 1 Hatch 1 Basis Doc-VIP75.doc Page 7 of 46 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.

CATEGORY C VIP-75 WELD SELECTION 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) one examination performed within two cycl es of operation after the SI and one additional examination performed, using qua lified procedures, with no evidence of cracking, or b) a preservice (post-stress improvement) and inservice examination with a qualified procedure with no cracking identified, or c) at least one examination performed with a qualified procedure after more than two operating cycles and no cracking detected fo r welds that were previously stress-improved but did not receive a preservice examination

With effective HWC combined with resistant materials, the scope may be further reduced to 10% of the population.

The scope of welds consists of dissimilar me tal welds shown in Table 3 and Table 4 and similar metal welds shown in Table 5 and Table 6. The welds for each of the tables are discussed below.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 8 of 46 Rev.1.0 Table 3 Welds

Table 3 lists eight dissimilar metal welds. These welds have been evaluated against the VIP-75 criteria pertaining to: (1) effective stress improvement, (2) hydrogen water protection, and (3) pre-requisite examinations using qualified procedures. The evaluations are shown below.

Effective Stress Improvement - Seven of the eight welds received an effective stress improvement treatment in 1993 using the MSIP process. Weld 1E11-1RHR-24A-R-12 received an effective IHSI stress improvement as defined by the parameters in Appendix C.

Hydrogen Water Protection - Hydrogen protection was not credited for any of the eight welds because there is no flow in th e area of the welds (see Appendix B).

Pre-requisite Qualified Examinations - Those welds highlighted in yellow satisfy the requirement to perform at least one examination (beyond the baseline performed after the stress improvement) using a "qualified" procedure, as defined in Appendix A. In many cases, multiple examinations were performed. Welds 1E21-1CS-10A-18A, 1E21-1CS-10B-19A, and 1E11-1RHR-24A-R-12 have examination coverage limitations due to weld crown/taper issues, and credit was not taken for these examinati ons. Issues and actions for each weld is discussed below.

1E21-1CS-10A-18A and 1E21-1CS-10B-19A

Each of these welds has a small weld cr own and a significant taper on the safe-end extension side of each weld that interferes with performing the Appendix VIII UT exam. Weld modifications cannot be performed to off-set the effect of the taper (except for a weld overlay). Below is a proposed action plan.

1. Perform ultrasonic exams during 1R22.

2. Using a flaw-tolerance evaluation, evaluate the data to determine if there is reasonable assurance of structural integrity as required by 10 CFR 50.55a(g)(6)(i).

3. Develop a relief request.

1E11-1RHR-24A-R-12

There is a small weld crown and a significant ta per on the valve side th at interferes with performing the Appendix VIII UT exam. Weld modifications cannot be performed to off-set the effects of the taper (except for a we ld overlay); however, grinding off the weld crown may be beneficial. Be low is a proposed action plan.

1. Prior to 1R22, obtain minimum wall values for these welds.

2. Take detailed dimensions a nd grind areas as needed.

3. Perform ultrasonic exams during 1R22.

4. Using a flaw-tolerance evaluation, evaluate the data to determine if there is reasonable assurance of structural integrity as required by 10 CFR 50.55a(g)(6)(i).

5. Develop a relief request.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 9 of 46 Rev.1.0 Without hydrogen protection, a 25% samp le of these welds (or 2 welds) is required every ten years. Per the NRC Final SE dated May 14, 2002, when using the reduced scope, the locations to be examined should be selected us ing risk insights to se lect risk significant piping. Risk significant piping is defined as locations with a high consequence of failure and susceptibility to some type of failure mechanism. Generally this includes (1) Reactor Coolant Pressure Boundary (RCPB) piping that supports an ECCS function (mitigation) or (2) performs an outboard containment isolation function between the containment penetration and the outboard isolation valve.

Piping that functions only as the RCPB would generally have lower risk.

None of the eight welds in Table 3 have an outboard containment function; however, five welds - 1E11-1RHR-24A-R-12, 1E21-1CS-10A-18A, 1E21-1CS-10A-20A, 1E21-1CS-10B-19A, and 1E21-1CS-10B-21A have ECCS functions.

During the selection of the actual welds for examination, the requirements are to consider locations where IGSCC could be accelerated by crevice corrosion or thermal fatigue. In addition, locations having attributes that would promote IGSCC should have higher priority for inspection. The attributes that may be c onsidered include: high carbon or low ferrite content, crevice or stagnant flow condition, ev idence of weld repair, surface cold work, and high fit-up, residual and operating stresses. This requirement is implemented using, "Weld Prioritization for Adoption of BWRVIP-75 at Edwin I. Hatch Unit 1 and Unit 2", dated June 2001. Structural Integrit y Associates (SIA) stated 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 incl ude: high carbon or low ferrite co ntent, crevice or stagnant flow conditions, evidence of weld repair, su rface cold work, and high fit-up, residual and operating stresses. Each weld in Table 3, except for the CRD cap weld (1C11-1CRD-3-R-18A which is outside the scope of GL-88-01/NUREG-0313 due to its small diameter) has an SIA Priority of 1, which indicates that IGSCC growth/initiation should be about the same. Therefore, any of the 5 welds in Table 3 having an ECCS function may be selected.

Summary Welds 1E21-1CS-10A-18A, 1E21-1CS-10B-19A, and 1E11-1RHR-24A-R-12 will be re-examined during 1R22 to satisfy pre-requisite conditions.

ECCS welds 1E21-1CS-10A-20A (SIA Priority 1) and 1E21-1CS-10B-21A (Priority 1) will be examined during 1R22 to complete the 25% sample criteria for the 3 rd Interval. These welds are highlighted in Red.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 10 of 46 Rev.1.0 Table 4 Welds

Table 4 lists ten dissimilar metal welds. These ten welds have been evaluated against the VIP-75 criteria pertaining to: (1) effective stress improvement, (2) hydrogen water protection, and (3) pre-requisite examinations using qualified procedures. The evaluations are shown below.

Effective Stress Improvement - Each of the ten welds received an effective IHSI stress improvement as defined by the parameters in Appendix C.

Hydrogen Water Protection - Hydrogen protection was credite d each of the ten welds (see Appendix B).

Pre-requisite Qualified Examinations - Those welds highlighted in yellow satisfy the requirement to perform at least one examination (beyond the baseline performed after the stress improvement) using a "qualified" procedure, as defined in Appendix A. In many cases, multiple examinations were performed. 1B31-1RC-12AR-J-5, 1B31-1RC-12BR-A-5, 1B31-1RC-12BR-B-5, 1B31-1RC-28A-1, and 1B31-1RC-28B-1 have examination data issues such that credit has not yet been taken for previous examinations. Each of these welds will be re-examined in 1R22. After the 1R22 exams, if it was determined that there no previous exam issues with a weld, then the previous data for the weld may be used to satisfy the pre-requisites.

With hydrogen protection, a 10% sample of the ten welds (or 1 weld) is required to be examined every ten years. Per the NRC Final SE dated May 14, 2002, when using the reduced scope, the locations to be examined shou ld be selected using risk insights to select risk significant pipi ng. Risk significant piping is defined as locations with a high consequence of failure and susceptibility to some type of failure mechanism. Generally this includes (1) Reactor Coolant Pressure Boundary (RCPB) piping that supports an ECCS function (mitigation) or (2) performs an outboard containment isolation function between the containment penetration and the outboard isolation valve.

Piping that functions only as the RCPB would generally have lower risk.

None of the ten welds have an outboard cont ainment function; however, all welds except 1B31-1RC-28A-1, and 1B31-1RC-28B

-1 have ECCS functions.

During the selection of the actual welds for examination, the requirements are to consider locations where IGSCC could be accelerated by crevice corrosion or thermal fatigue. In addition, locations having attributes that would promote IGSCC should have higher priority for inspection. The attributes that may be c onsidered include: high carbon or low ferrite content, crevice or stagnant flow condition, ev idence of weld repair, surface cold work, and high fit-up, residual and operating stresses. This requirement is implemented using, "Weld Prioritization for Adoption of BWRVIP-75 at Edwin I. Hatch Unit 1 and Unit 2", dated June 2001. Structural Integrit y Associates (SIA) stated 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 incl ude: high carbon or low ferrite co ntent, crevice or stagnant FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 11 of 46 Rev.1.0 flow conditions, evidence of weld repair, su rface cold work, and high fit-up, residual and operating stresses. Each weld in Table 4 has an SIA Priority of 1, which indicates that IGSCC growth/initiation should be about the same. Therefore, any of the 8 welds in Table 4 having an ECCS function may be selected.

Summary After the 1R22 outage examinations, one of the ECCS welds will be designated as meeting the 10% examination for the 3 rd Interval. Similarly an ECCS weld will be selected for the 4 th Interval.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 12 of 46 Rev.1.0 Table 5 Welds

Table 5 lists ten similar metal welds. These welds have been evaluated against the VIP-75 criteria pertaining to: (1) effective stress improvement, (2) hydrogen water protection, and (3) pre-requisite examinations using qualif ied procedures. The evaluations are shown below.

Effective Stress Improvement - Four of the seven welds received an effective stress improvement treatment in 1993 using the MSIP process. Welds 1B31-1RC-4B-1A, 1B31-1RC-4B-10A, and 1E11-1RHR-20B-D-2 received an effective IHSI stress improvement as defined by the parameters in Appendix C.

Hydrogen Water Protection - Hydrogen protection was not credited for any of the seven welds because there is no flow in th e area of the welds (see Appendix B).

Pre-requisite Qualified Examinations - Those welds highlighted in yellow satisfy the requirement to perform at least one examination (beyond the baseline performed after the stress improvement) using a "qualified" procedure, as defined in Appendix A. In many cases, multiple examinations were performed.

Without hydrogen protection, a 25% sample of the ten welds (or 3 welds) is required to be examined every ten years. Per the NRC Final SE dated May 14, 2002, when using the reduced scope, the locations to be examined shou ld be selected using risk insights to select risk significant pipi ng. Risk significant piping is defined as locations with a high consequence of failure and susceptibility to some type of failure mechanism. Generally this includes (1) Reactor Coolant Pressure Boundary (RCPB) piping that supports an ECCS function (mitigation) or (2) performs an outboard containment isolation function between the containment penetration and the outboard isolation valve.

Piping that functions only as the RCPB would generally have lower risk.

None of the ten welds have an outboard contai nment function; however, all of the ten welds except 1B31-1RC-4JP-A-2 and 1B31-1 RC-4JP-B-2 have ECCS functions.

During the selection of the actual welds for examination, the requirements are to consider locations where IGSCC could be accelerated by crevice corrosion or thermal fatigue. In addition, locations having attributes that would promote IGSCC should have higher priority for inspection. The attributes that may be c onsidered include: high carbon or low ferrite content, crevice or stagnant flow condition, ev idence of weld repair, surface cold work, and high fit-up, residual and operating stresses. This requirement is implemented using, "Weld Prioritization for Adoption of BWRVIP-75 at Edwin I. Hatch Unit 1 and Unit 2", dated June 2001. Structural Integrit y Associates (SIA) stated 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 incl ude: high carbon or low ferrite co ntent, crevice or stagnant flow conditions, evidence of weld repair, su rface cold work, and high fit-up, residual and operating stresses. Each weld in Table 5 has an SIA Priority of 4, which indicates that FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 13 of 46 Rev.1.0 IGSCC growth/initiation should be about the same. Therefore, any of the 8 welds in Table 5 having an ECCS function may be selected.

Summary Each weld in this table has an SIA Priority of 4; therefore, any of the welds having an ECCS function may be selected.

Welds 1B31-1RC-4B-10A, 1E11-1RHR-20B-D-2 and 1E21-1CS-10B-20A will be examined during 1R22 to meet the 25% sample criteria for the 3 rd Interval. These welds are highlighted in Red. Weld 1E21-1CS-10A-19A will also be examined in 1R22 as part of the 4 th Interval requirements. This weld is highlighted in Green.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 14 of 46 Rev.1.0 Table 6 Welds

Table 6 lists fifty-four similar metal welds. These welds have been evaluated against the VIP-75 criteria pertaining to: (1) effective stress improvement, (2) hydrogen water protection, and (3) pre-requisite examinations using qualified procedures. The evaluations are shown below.

Effective Stress Improvement

- All fifty-four of the welds received an effective IHSI stress improvement as defined by the parameters in Appendix C.

Hydrogen Water Protection - Hydrogen protection was credited for all of these welds (see Appendix B).

Pre-requisite Qualified Examinations - Those welds highlighted in yellow satisfy the requirement to perform at least one examination (beyond the baseline performed after the stress improvement) using a "qualified" procedure, as defined in Appendix A. In many cases, multiple examinations were performed.

With hydrogen protection, a 10% sample of the 54 welds (or 6 welds) is required to be examined every ten years. Per the NRC Final SE dated May 14, 2002, when using the reduced scope, the locations to be examined shou ld be selected using risk insights to select risk significant pipi ng. Risk significant piping is defined as locations with a high consequence of failure and susceptibility to some type of failure mechanism. Generally this includes (1) Reactor Coolant Pressure Boundary (RCPB) piping that supports an ECCS function (mitigation) or (2) performs an outboard containment isolation function between the containment penetration and the outboard isolation valve.

Piping that functions only as the RCPB would generally have lower risk.

During the selection of locations for inspection, consideration should be given re garding locations where IGSCC could be accelerated by crevice corrosion or thermal fatigue. In addition, locations having attributes that would promote IGSCC should have higher priority for inspection. The attributes that may be considered include: high carbon or low ferrite content, crevi ce or stagnant flow condition, evidence of weld repair, surface cold work, and high fit-up, residual and operating stresses.

During the selection of the actual welds for examination, the requirements are to consider locations where IGSCC could be accelerated by crevice corrosion or thermal fatigue. In addition, locations having attributes that would promote IGSCC should have higher priority for inspection. The attributes that may be c onsidered include: high carbon or low ferrite content, crevice or stagnant flow condition, ev idence of weld repair, surface cold work, and high fit-up, residual and operating stresses. This requirement is implemented using, "Weld Prioritization for Adoption of BWRVIP-75 at Edwin I. Hatch Unit 1 and Unit 2", dated June 2001. Structural Integrit y Associates (SIA) stated 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 incl ude: high carbon or low ferrite co ntent, crevice or stagnant flow conditions, evidence of weld repair, su rface cold work, and high fit-up, residual and operating stresses.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 15 of 46 Rev.1.0

Summary ECCS welds 1B31-1RC-28A-13 (SIA Priority 2), 1B31-1RC-28A-16 (SIA Priority 2), 1B31-1RC-28A-17 (SIA Priority 2), and 1B31-1RC-12AR-22AM-3 (SIA Priority 2) were examined during 1R17 for 3 rd Interval credit.

ECCS welds 1B31-1RC-12BR-E-1 (SIA Priority

3) and 1B31-1RC-28B-17 (SIA Priority 2) will be examined during 1R22 to complete the 3 rd Interval requirements. These welds are highlighted in Red.

ECCS weld 1B31-1RC-12BR-A-1 (SIA Priority 4) and containment isolation weld 1G31-1RWCUM-6-D-16 (SIA Priority 2) will be examined during 1R22 for 4 th Interval credit. These welds are highlighted in Green.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 16 of 46 Rev.1.0 CATEGORY E WELDS

Category E welds are those welds with a full-str uctural overlay. GL 88-01 specifies that the entire population is to be examined once every two refueling cycles.

New Category E Examination Frequency To use the BWRVIP-075 reduced inspection criteria, the licensee must first ensure that the weld received a post overlay inspection and inservice examination with a "qualified" procedure (three party agreement or Appendix VIII).

If the above requirements are met, the BWRVIP

-075 reduced inspection criteria of 25% of the population may be used. With effective HWC, the scope may be further reduced to 10% of the population. Table 7 lists the examination requirements for those overlays with effective hydrogen water protection per Appendix B. Table 8 lists the examination requirements for those overlays without effective hydrogen water protection per Appendix B. The weld in each of these tables are discussed below:

Table 7 Table 7 lists forty-eight welds with overlays. These welds ha ve been evaluated against the VIP-75 criteria pertaining to: (1) pre-requisite examinations using qualified procedures and (2) hydrogen water protection. The evaluations are shown below.

Pre-requisite Qualified Examinations - Initial weld overlays were applied in 1982 and in 1984. These overlays were resurfaced in 1986. Examinations performed after the 1986 resurfacing are considered to be qualified examinations (shown in yellow in Table 7) based on the following:

The 1986 resurfacing provided a surface condition acceptable for current PDI examinations. The techniques used are essentially the same techniques as currently used for PDI examinations.

Hydrogen Water Protection - Hydrogen protection was credited for all of these overlays (see Appendix B).

Summary A 10% sample of the 48 welds (or 5 welds) is required to be examined each 10-year interval, with 50% examined within the first si x years of the interval. Five of the welds (shown in Red in Table 7) were examined in 1999 (1R18) and satisfied this requirement.

Three welds (60% of the population shown in Green) will be examined during 1R22 for 4 th Interval credit.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 17 of 46 Rev.1.0 Table 8 Table 8 lists six welds with overlays. These welds have been evalua ted against the VIP-75 criteria pertaining to: (1) pre-requisite examinations usi ng qualified procedures and (2) hydrogen water protection. The ev aluations are shown below.

Pre-requisite Qualified Examinations - Initial weld overlays were applied in 1982 and in 1984. These overlays were resurfaced in 1986. Examinations performed after the 1986 resurfacing are considered to be qualified examinations (shown in yellow in Table 8) based on the following:

The 1986 resurfacing provided a surface condition acceptable for current PDI examinations. The techniques used are essentially the same techniques as currently used for PDI examinations.

Hydrogen Water Protection - Hydrogen protection was not credited for these overlays (see Appendix B).

Summary A 25% sample of the six welds (or 2 welds) is required to be examined each 10-year interval with 50% examined within the first six years of the interval. One of the welds (shown in Red in Table 8) was examined in 1999 (1R18) and one will be examined in 1R22 to satisfy this requirement.

One weld (shown in Green) will be examined during 1R22 for 4 th Interval credit.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 18 of 46 Rev.1.0 ADDITIONAL WELDS There are two welds not previously eval uated - 1B31-1RC-28A-8BC and 1B31-1RC-28B-9BC. These are the welds joining the barrel of 4" Long Weld Neck Flanges to the 28" Recirculation Pipe (See S-15251).

Pipe Specification DCA would apply to this piping. Per A-11000, flanges for 3-1/2" piping and larger are 900# flanges. While the manufacturer of the HNP-1 flange is undetermined, all 900# st ainless steel flanges should be relatively similar. A 4"nominal 900# Texas Flange has a 4" bore and the OD of the barrel is 6.25".

The length of the flange is 12". This appears to be the same as found at HNP-1. Branch connection fittings (e.g., sweepol et) were not used for these welds. Instead, a "set on" configuration or "set in

" configuration was used.

Because these configurations have less weld volume, thus less heat input; therefore, there should have been less sensitizati on and less residual stresses than for butt welds; therefore, the potential for IGSCC should be less. Theref ore, they were not categorized per GL 88-01/NUREG-0313. Stress improvement was not considered necessary or needed on these welds because of their configuration. and they have not been examined in the past.

If the configuration is "set-on" such as shown in Figure IWB-2500-10 of Section XI, meaningful UT examinations are not practical because the weld is lo cated on top of the 28" pipe. A surface examination is the only practical examination for this configuration.

If the configuration is "set-in" such as shown in Figure IWB-2500-11 of Section XI, one-sided UT examinations can be performed during from the 28" pipe.

These welds will be examined during 1R22 with the methodology determined by the Level

III.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 19 of 46 Rev.1.0 TABLE 2 GL 88-01 CATEGORY A RWCU WELDS - CODE CATEGEORY B-J WELDS (All Welds Received an MSIP Treatment Except the Two Welds in the Penetration and there is hydrogen protection) 10% Sample Of 19 Welds In This Population (2 Welds)

INTERVAL 3 INTERVAL 4 PERIOD 1 PERIOD 2 PERIOD 3 Effective H 2 Chemistry?

SIA Priority ECCS or CIV 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 1. 1G31-1RWCUM-6-D-2 YES 4 NO V 2. 1G31-1RWCUM-6-D-3 YES 4 NO

3. 1G31-1RWCUM-6-D-4 YES 2 NO V&S 4. 1G31-1RWCUM-6-D-5 YES 2 NO V&S V&S 5. 1G31-1RWCUM-6-D-6 YES 4 NO

6. 1G31-1RWCUM-6-D-7 YES 4 NO

7. 1G31-1RWCUM-6-D-8 YES 4 NO V&S 8. 1G31-1RWCUM-6-D-10 YES 4 NO V&S 9. 1G31-1RWCUM-6-D-10A YES 4 NO

10. 1G31-1RWCUM-6-D-11 YES 4 NO

11. 1G31-1RWCUM-6-D-12 YES 4 NO

12. 1G31-1RWCUM-6-D-13 YES 4 NO

13. 1G31-1RWCUM-6-D-14 YES 2 NO V&S 14. 1G31-1RWCUM-6-D-15B (304L pipe to 304L pipe in Penetration) YES 4 NO 15. 1G31-1RWCUM-6-D-15C (Flued head with corrosion resistant 308L cladding to 304L pipe in Penetration) YES 4 NO 16. 1G31-1RWCUM-6-D-17 YES 4 YES 17. 1G31-1RWCUM-6-D-18 YES 4 YES 18. 1G31-1RWCUM-6-D-19 YES 4 YES 19. 1G31-1RWCUM-6-D-20 YES 2 YES VOL Weld examination credited for 3 rd Interval Weld examination credited for 4 th Interval

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 20 of 46 Rev.1.0 TABLE 3 GL 88-01 CATEGORY C WELD DISSIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT WITHOUT EFFECTIVE HYROGEN WATER CHEMISTRY 25% Sample Of Eight Welds In This Population After One Qualified Weld Examinations (2 Welds) 1 st Period 3 rd Interval 2 nd Period 3 rd Interval 3 rd Period 3 rd Interval Cat C (B-F) Exam Issue? Crown or Taper ? Repai red ? E C C S 2 nd Interval 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 1. 1B31-1RC-4JP-A-1 MSIP 1993 SIA Priority 1 NO NO YES N (1993B) UT-H-409/07 (1994) UT-H-409/08 UT-H-409

2. 1B31-1RC-4JP-B-1 MSIP 1993 SIA Priority 1 NO NO YES N (1993B) UT-H-409/07 (1994) UT-H-409/08 ES-MISN-H-409 Version 1

3. 1C11-1CRD-3-R-18A MSIP 1993 Not Categorized by SIA NO NO N (1993B) GE-UT-208/1 UT-H-409/7 (1994) UT-HAT-208V0/00 UT-H-409/8 4. 1E11-1RHR-24A-R-12 IHSI 1986 04800-2183 SIA Priority 1 YES YES YES 86B 88 (1990) UT-H-409/6 GE-UT-200/0 (1991) UT-H-810/1 (1994) UT-HAT-208V0/00 UT-H-409/8 Man Pickup

VOL FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 21 of 46 Rev.1.0 TABLE 3 GL 88-01 CATEGORY C WELD DISSIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT WITHOUT EFFECTIVE HYROGEN WATER CHEMISTRY 25% Sample Of Eight Welds In This Population After One Qualified Weld Examinations (2 Welds) 1 st Period 3 rd Interval 2 nd Period 3 rd Interval 3 rd Period 3 rd Interval Cat C (B-F) Exam Issue? Crown or Taper ? Repai red ? E C C S 2 nd Interval 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 5. 1E21-1CS-10A-18A MSIP 1993 SIA Priority 1 YES YES YES (1993B) GE-UT-208/1 UT-H-409/7 (1994) UT-HAT-208V0/00 UT-H-409/8 VOL 6. 1E21-1CS-10A-20A MSIP 1993 SIA Priority 1 NO NO YES (1993B) GE-UT-209/1 (1994) UT-HAT-209V0/00 VOL 7. 1E21-1CS-10B-19A MSIP 1993 SIA Priority 1 YES YES YES (1993B) GE-UT-208/1 UT-H-409/7 (1994) UT-HAT-208V0/00 UT-H-409/8 VOL 8. 1E21-1CS-10B-21A MSIP 1993 SIA Priority 1 NO NO YES (1993B) GE-UT-209/1 (1994) UT-HAT-209V0/00 VOL Weld examination satisfied the requirement for a "qualified" examination prior to using the VIP-75 reduced examination scope. Weld examination credited for 3 rd Interval Weld examination credited for 4 th Interval Weld examination does not satisfy the requirement for a "qualified" examination because of the weld contour issues existing during the exams.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 22 of 46 Rev.1.0 TABLE 4 GL 88-01 CATEGORY C DISSIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HYROGEN WATER CHEMISTRY 10% Sample Of Ten Welds In This Population After One Qualified Weld Examinations (1 Weld) 2 nd Interval Prev. Exam Issue? Crown or Taper R e p a i r E C C P1 P2 P3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 1. 1B31-1RC-12AR-F-5 IHSI 1986 04800-2206 SIA Priority 1 NO NO YES YES 86B 87 88 1990 (1991) UT-H-810/1 - UT-HAT-225DV2 2. 1B31-1RC-12AR-G-5 IHSI 1986 04800-2220 SIA Priority 1 NO NO YES YES 86B 88 91 (1993) GE-UT-209/1 UT-HAT-225DV2 UT-H-409 Man Pick 3. 1B31-1RC-12AR-H-5 IHSI 1986 04800-2261 SIA Priority 1 NO NO YES YES 86B 88 91 (1993) GE-UT-209/1 (1994) UT-HAT-209V0/00 UT-HAT-225DV2 UT-H-409 Man Pick 4. 1B31-1RC-12AR-J-5 IHSI 1986 04800-2300 SIA Priority 1 YES NO NO YES 86B 87 88 - (1993) GE-UT-209/1 (1994) UT-HAT-209V0/00 UT-HAT-225DV2 VOL 5. 1B31-1RC-12AR-K-5 IHSI 1986 04800-2338 SIA Priority 1 NO NO NO YES 86B 87 88 (1990) UT-H-409/6 - UT-H-409

6. 1B31-1RC-12BR-A-5 IHSI 1986 04800-2559 SIA Priority 1

YES NO YES YES 86B 87 88 (1990) UT-H-409/6 - VOL FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 23 of 46 Rev.1.0 TABLE 4 GL 88-01 CATEGORY C DISSIMILAR METAL WELDS WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HYROGEN WATER CHEMISTRY 10% Sample Of Ten Welds In This Population After One Qualified Weld Examinations (1 Weld) 2 nd Interval Prev. Exam Issue? Crown or Taper R e p a i r E C C P1 P2 P3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 7. 1B31-1RC-12BR-B-5 IHSI 1986 04800-2575 SIA Priority 1 YES NO NO YES 86B 87 88 (1990) UT-H-409/6 - VOL 8. 1B31-1RC-12BR-D-5 IHSI 1986 04800-2603 SIA Priority 1 NO NO YES YES 86B 88 91 (1993) GE-UT-209/1 (1994) UT-HAT-209V0/00 UT-HAT-225DV2 9. 1B31-1RC-28A-1 IHSI 1986 04800-1736 SIA Priority 1 YES NO NO NO 86B 87 (1990) UT-H-409/6 (1991) UT-H-810/1 UT-H-409/7 Man Pick - VOL 10. 1B31-1RC-28B-1 IHSI 1986 04800-2016 SIA Priority 1 YES NO NO NO 86B 87 (1990) UT-H-409/6 (1991) UT-H-810/1 - VOL Weld examination satisfied the requirement for a "qualified" examination prior to using the VIP-75 reduced examination scope. Weld examination credited for 3 rd Interval Weld examination credited for 4 th Interval Weld examination may not satisfy the requirement for a "qualified" examination because of issues with data. After the 1R22 exams if it was determined that there no previous exam issues then the previous data may be used.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 24 of 46 Rev.1.0 TABLE 5 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITHOUT EFFECTIVE HWC 25% Sample Of Ten Welds In This Population After One Qualified Weld Examinations (3 Welds) P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Priority ECCS 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 1. 1B31-1RC-4A-1A IHSI-1986 04800-1780 Treated with 28A-12BC 4 YES 86B (1987) UT-H-401/6 UT-H-402

2. 1B31-1RC-4A-10A IHSI-86 04800-2451 Treated with 28A-15BC-1 4 YES 86B (1987) UT-H-401/6 UT-H-402 VOL 3. 1B31-1RC-4B-1A IHSI-1986 04800-1780 Treated with 28B-12BC 4 YES 86B (1988) UT-H-401/6 - (1994) UT-H-400/12 4. 1B31-1RC-4B-10A IHSI-86 04800-2451 Treated with 28B-15BC-1 4 YES 86B (1988) UT-H-401/6 - (1994) UT-H-400/12 5. 1B31-1RC-4JP-A-2 MSIP-93 4 NO NA NA (1993B)

UT-H-400/11 (1994) UT-H-400/12 UT-H-402

6. 1B31-1RC-4JP-B-2 MSIP-93 4 NO NA NA (1993B)

UT-H-400/11 (1994) UT-H-400/12 7. 1E11-1RHR-20B-D-2 IHSI-86 04800-2527 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 - VOL 8. 1E21-1CS-10A-19A MSIP-1993 4 YES NA NA (1993B)

GE-UT-208/1 (1994) UT-HAT-208V0/0 VOL FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 25 of 46 Rev.1.0 TABLE 5 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITHOUT EFFECTIVE HWC 25% Sample Of Ten Welds In This Population After One Qualified Weld Examinations (3 Welds) P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Priority ECCS 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 9. 1E21-1CS-10B-20A MSIP-1993 4 YES NA NA 1993B)

GE-UT-208/1 (1994) UT-HAT-208V0/0 VOL 10. 1E11-1RHR-24A-R-14 IHSI-86 04800-2195 4 YES (1990) UT-H-400/9 (1991) GE-UT-208/1 Weld examination satisfied the requirement for a "qualified" examination prior to using the VIP-75 reduced examination scope. Weld examination credited for 3 rd Interval Weld examination credited for 4 th Interval FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 26 of 46 Rev.1.0 TABLE 6 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HWC 10% Sample Of Fifty-Four Welds In This Population After One Qualified Weld Examination (6 Welds)

P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Prior ECCS/ CONT 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 1. 1B31-1RC-12AR-G-2 IHSI-86 04800-1563 4 YES 86B (1988) UT-H-400/7 (1990) GE-UT-200/0 (1994) UT-HAT-208V0/0 UT-HAT-225DV2

2. 1B31-1RC-12AR-J-2 IHSI-86 04800-1151 4 YES 86B 87 (1990) GE-UT-200/0 UT-H-402

3. 1B31-1RC-12AR-J-4 IHSI-86 04800-1588 4 YES 86B 87 (1990) GE-UT-200/0 (1993) GE-UT-208/1 (1994) UT-HAT-208V0/0 UT-H-402 UT-HAT-225DV2 4. 1B31-1RC-12AR-K-4 IHSI-86 04800-1600 4 YES 86B 87 (1990) GE-UT-200/0 UT-HAT-225DV2

5. 1B31-1RC-12BR-A-2 IHSI-86 04800-1893 4 YES 86B 87 (1990) GE-UT-200/0 (1994) UT-HAT-208V0/0 6. 1B31-1RC-12BR-A-3 IHSI-86 04800-1903 4 YES 86B 87 (1990) GE-UT-200/0 (1994) UT-HAT-208V0/0 7. 1B31-1RC-12BR-B-2 IHSI-86 04800-1933 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 8. 1B31-1RC-12BR-B-4 IHSI-86 04800-1953 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 9. 1B31-1RC-12BR-D-4 IHSI-86 04800-1986 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 (1993) UT-H-400/11 GE-UT-208/1 10. 1B31-1RC-22AM-1BC-1 IHSI-86 04800-1106 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 UT-H-402 FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 27 of 46 Rev.1.0 TABLE 6 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HWC 10% Sample Of Fifty-Four Welds In This Population After One Qualified Weld Examination (6 Welds)

P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Prior ECCS/ CONT 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 11. 1B31-1RC-22AM-1BC-2 IHSI-86 04800-1527 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 UT-H-402

12. 1B31-1RC-22AM-3BC-1 IHSI-86 04800-1538 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 UT-H-402

13. 1B31-1RC-22AM-3BC-2 IHSI-86 04800-1551 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 UT-H-402

14. 1B31-1RC-22BM-1BC-1 IHSI-86 04800-1824 4 YES 86B (1988) UT-H-400/7 (1993) UT-H-400/11 15. 1B31-1RC-22BM-1BC-2 IHSI-86 04800-1835 4 YES 86B (1988) UT-H-400/7 (1993) UT-H-400/11 16. 1B31-1RC-22BM-3BC-1 IHSI-86 04800-1870 4 YES 86B (1988)

UT-H-400/7 (1993) UT-H-400/11 17. 1B31-1RC-22BM-3BC-2 IHSI-86 04800-1882 4 YES 86B (1988) UT-H-400/7 (1993) UT-H-400/11 18. 1B31-1RC-28A-5 IHSI-86 04800-1669 4 NO 86B (1988) UT-H-400/7 (1990) UT-H-400/9 19. 1B31-1RC-28A-5A IHSI-86 04800-2026 4 NO 86B (1988) UT-H-400/7 (1990) UT-H-400/9 20. 1B31-1RC-28A-11 IHSI-86 04800-1485 2 NO 86 (1988) UT-H-400/7 (1990) UT-H-400/9 (1991) GE-UT-208/1 UT-H-400/10 (1994) UT-HAT-208V0/0 UT-H-400/12 UT-H-402 UT-HAT-225DV2 FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 28 of 46 Rev.1.0 TABLE 6 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HWC 10% Sample Of Fifty-Four Welds In This Population After One Qualified Weld Examination (6 Welds)

P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Prior ECCS/ CONT 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 21. 1B31-1RC-28A-11BC 4" Sweepolet IHSI-86 04800-2130 4 YES 86B (1988) UT-H-400/7 (1994) UT-H-400/12 UT-H-402

22. 1B31-1RC-28A-13 IHSI-86 04800-1507 2 YES 86B (1988) UT-H-400/7 (1990) UT-H-400/9 (1991) GE-UT-212/1 (1994) UT-HAT-208V0/0

UT-HAT-225DV2

23. 1B31-1RC-28A-14BC 4" Sweepolet IHSI-86 04800-1684 4 YES 86B (1988) UT-H-400/7 (1991) UT-H-400/10 (1994) UT-400/12 UT-H-402

24. 1B31-1RC-28A-15 IHSI-86 04800-1693 4 YES 86B (1988) UT-H-400/7 (1990) UT-H-400/9 (1991) GE-UT-208/1 (1994) UT-HAT-208V0/0 UT-HAT-225DV2

25. 1B31-1RC-28A-16 IHSI-86 04800-1082 2 YES 86B (1988) UT-H-400/7 (1990) UT-H-400/9 GE-UT-200/0 (1991) UT-H-400/10 (1994) UT-HAT-208V0/0 UT-H-400/12 UT-H-402 UT-HAT-225DV2 26. 1B31-1RC-28A-17 IHSI-86 04800-1060 2 YES 86B (1988) UT-H-400/7 (1990) UT-H-400/9 (1991) UT-H-400/10 (1994) UT-H-400/12 UT-H-402

27. 1B31-1RC-28B-5 IHSI-86 04800-1758 4 NO 86B (1990) UT-H-400/9 (1991) GE-UT-208/1 UT-H-400/10 (1993) GE-UT-208/1 28. 1B31-1RC-28B-6 IHSI-86 04800-1770 4 NO 86B (1988) UT-H-400/7 (1990) GE-UT-200/0 (1993) GE-UT-208/1 FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 29 of 46 Rev.1.0 TABLE 6 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HWC 10% Sample Of Fifty-Four Welds In This Population After One Qualified Weld Examination (6 Welds)

P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Prior ECCS/ CONT 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 29. 1B31-1RC-28B-12 IHSI-86 04800-1181 2 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 GE-UT-200/0 30. 1B31-1RC-28B-12BC 4" Sweepolet IHSI-86 04800-1780 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 (1991) UT-H-400/10 -

31. 1B31-1RC-28B-15BC 4" Sweepolet IHSI-86 04800-2451 4 YES 86B (1988) UT-H-400/7 - (1994) UT-H-400/12 32. 1B31-1RC-28B-17 IHSI-86 04800-1800 2 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 GE-UT-200/0 (1991) UT-H-400/10 - VOL 33. 1G31-1RWCU-6-D-15A IHSI-86 04800-1402 2 NO 86B (1987) UT-H-400/7 - - UT-H-402

34. 1G31-1RWCUM-6-D-16 MSIP 1993 316 NG Piping to Original Flued Head 2 YES 88B (1991) UT-H-400/10 (1993) UT-H-400/11 (1994) UT-H-400/12 VOL 35. 1B31-1RC-12AR-F-1 IHSI-86 04800-1705

4 YES 86B 87 (1990) GE-UT-200/0 (1991) GE-UT-208/1 - UT-H-402

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 30 of 46 Rev.1.0 TABLE 6 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HWC 10% Sample Of Fifty-Four Welds In This Population After One Qualified Weld Examination (6 Welds)

P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Prior ECCS/ CONT 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 36. 1B31-1RC-12AR-G-1 IHSI-86 04800-1060, 1118 4 YES 86B (1988) UT-H-400/7 - (1994) UT-H-400/12 UT-H-402

37. 1B31-1RC-12AR-H-1 IHSI-86 04800-1578 4 YES 86B (1988) UT-H-400/7 - (1994) UT-H-400/12 UT-H-402

38. 1B31-1RC-12AR-J-1 IHSI-86 04800-1138 4 YES 86B (1988) UT-H-400/7 (1991) GE-UT-208/1 UT-H-400/10 - UT-H-402

39. 1B31-1RC-12AR-K-1 IHSI-86 04800-1725 4 YES 86B (1988) UT-H-400/7 (1991) GE-UT-208/1 - UT-H-402

40. 1B31-1RC-12BR-A-1 IHSI-86 04800-2467 4 YES 86B 87 (1990) GE-UT-200/0 (1994) UT-H-400/12 VOL 41. 1B31-1RC-12BR-B-1 IHSI-86 04800-1923 4 YES 86B (1988) UT-H-400/7 (1991) GE-UT-208/1 - 42. 1B31-1RC-12BR-C-1 IHSI-86 04800-1965 4 YES 86B (1988) UT-H-400/7 - (1993) UT-H-400/11 43. 1B31-1RC-12BR-D-1 IHSI-86 04800-1976 4 YES 86B (1988) UT-H-400/7

- (1993) UT-H-400/11 44. 1B31-1RC-12BR-E-1 IHSI-86 04800-1996 3 YES 86B (1988) UT-H-400/7 - (1993) UT-H-400/11 VOL 45. 1B31-1RC-22AM-2 IHSI-86 04800-2144 3 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/8 GE-UT-200/0 - UT-H-402 UT-HAT-225DV2 FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 31 of 46 Rev.1.0 TABLE 6 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HWC 10% Sample Of Fifty-Four Welds In This Population After One Qualified Weld Examination (6 Welds)

P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Prior ECCS/ CONT 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 46. 1B31-1RC-22AM-3 IHSI-86 04800-2161 2 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/8 GE-UT-200/0 - UT-H-402

47. 1B31-1RC-22BM-2 IHSI-86 04800-1846 2 YES 86B (1988) UT-H-400/7 - (1993) UT-H-400/11 48. 1B31-1RC-22BM-3 IHSI-86 04800-1858 2 YES 86B (1988) UT-H-400/7 - (1993) UT-H-400/11 49. 1B31-1RC-28A-3 IHSI-86 04800-1030 4 NO 86B (1987)

UT-H-400/7 (1990) UT-H-400/9 (1991) GE-UT-208/1 (1993) GE-UT-208/1 50. 1B31-1RC-28A-9 IHSI-86 04800-1070 4 NO 86B (1987) UT-H-400/7 (1990) UT-H-400/9 (1991) GE-UT-208/1 UT-H-400/10

- UT-H-402 UT-HAT-225DV2 51. 1B31-1RC-28B-7 IHSI-86 04800-1161 4 NO 86B (1988) UT-H-400/7 (1990) UT-H-400/9 (1991) UT-H-800/02 UT-H-400/10 (1993) GE-UT-208/1 FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 32 of 46 Rev.1.0 TABLE 6 GL 88-01 CATEGORY C SIMILAR METAL WELD S WITH EFFECTIVE STRESS IMPROVEMENT WITH EFFECTIVE HWC 10% Sample Of Fifty-Four Welds In This Population After One Qualified Weld Examination (6 Welds)

P1 P2 P3 PERIOD 1 PERIOD 2 PERIOD 3 SIA Prior ECCS/ CONT 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 52. 1B31-1RC-28B-18 IHSI-86 04800-1811 2 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 (1991) UT-H-400/10 - 53. 1E11-1RHR-20B-D-1 IHSI-86 04800-2491 4 YES 86B (1987) UT-H-400/7 (1990) UT-H-400/9 -

54. 1E11-1RHR-20B-D-1BC IHSI-86 04800-2501 4 NO 86B (1987) UT-H-400/7 (1990) UT-H-400/9 Weld examination satisfied the requirement for a "qualified" examination prior to using the VIP-75 reduced examination scope. Weld examination credited for 3 rd Interval Weld examination credited for 4 th Interval

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 33 of 46 Rev.1.0 TABLE 7 GL 88-01 CATEGORY E WELD OVERLAYS WITH EFFECTIVE HWC 10% Sample After Two Qualified Weld Examinations (5 welds) Second Interval Volumetric Exams PERIOD 1 PERIOD 2 VIP-075 APPROVED PERIOD 3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 1. 1B31-1RC-12AR-F-2 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 SMART 1993 SMART 1994 SMART SMART EXAM 2. 1B31-1RC-12AR-F-3 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 PSCAN 1993 SMART 1994 SMART SMART EXAM 3. 1B31-1RC-12AR-F-4 1986 OVERLAY 1986 Baseline 1987, 1990, 1993 SMART 1994 SMART SMART EXAM 4. 1B31-1RC-12AR-G-3 1986 OVERLAY 1986 Baseline 1987, 1988, 1990, 1993 SMART 1994 SMART SMART EXAM 5. 1B31-1RC-12AR-G-4 1991 OVERLAY 1991 Baseline 1993 SMART 1994 SMART SMART EXAM 6. 1B31-1RC-12AR-H-2 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 SMART 1993 SMART 1994 SMART

SMART EXAM FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 34 of 46 Rev.1.0 TABLE 7 GL 88-01 CATEGORY E WELD OVERLAYS WITH EFFECTIVE HWC 10% Sample After Two Qualified Weld Examinations (5 welds) Second Interval Volumetric Exams PERIOD 1 PERIOD 2 VIP-075 APPROVED PERIOD 3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 7. 1B31-1RC-12AR-H-3 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 PSCAN 1993 SMART 1994 SMART SMART EXAM 8. 1B31-1RC-12AR-H-4 1986 OVERLAY 1986 Baseline 1987, 1990, 1991 PSCAN 1993 SMART 1994 SMART SMART EXAM 9. 1B31-1RC-12AR-J-3 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1988, 1990, 1991 PSCAN 1993 SMART 1994 SMART SMART EXAM 10. 1B31-1RC-12AR-K-2 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1988, 1990, 1991 SMART 1993 SMART 1994 SMART SMART EXAM 11. 1B31-1RC-12AR-K-3 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1988, 1990, 1991 PSCAN 1993 SMART 1994 SMART SMART EXAM 12. 1B31-1RC-12BR-A-4 1991 OVERLAY 1991 Baseline PSCAN 1994 SMART SMART EXAM FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 35 of 46 Rev.1.0 TABLE 7 GL 88-01 CATEGORY E WELD OVERLAYS WITH EFFECTIVE HWC 10% Sample After Two Qualified Weld Examinations (5 welds) Second Interval Volumetric Exams PERIOD 1 PERIOD 2 VIP-075 APPROVED PERIOD 3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 13. 1B31-1RC-12BR-B-3 1986 OVERLAY 1986 Baseline 1987, 1990, 1991 PSCAN 1994 SMART 14. 1B31-1RC-12BR-C-2 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1988, 1990, 1991 SMART 1994 SMART 15. 1B31-1RC-12BR-C-3 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1988, 1990, 1991 PSCAN 1994 SMART VOL 16. 1B31-1RC-12BR-C-4 1986 OVERLAY 1986 Baseline 1988, 1990, 1991 PSCAN 1994 SMART 17. 1B31-1RC-12BR-C-5 1988 OVERLAY 1986 Baseline 1988, 1990, 1991 Manual 1994 Manual 18. 1B31-1RC-12BR-D-2 1986 OVERLAY 1986 Baseline 1987, 1990, 1991 SMART 1993 SMART 1994 SMART 19. 1B31-1RC-12BR-D-3 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 PSCAN 1993 SMART 1994 SMART FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 36 of 46 Rev.1.0 TABLE 7 GL 88-01 CATEGORY E WELD OVERLAYS WITH EFFECTIVE HWC 10% Sample After Two Qualified Weld Examinations (5 welds) Second Interval Volumetric Exams PERIOD 1 PERIOD 2 VIP-075 APPROVED PERIOD 3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 20. 1B31-1RC-12BR-E-2 1984 OVERLAY 1986 RESURFACE 1986 Baseline 19887, 1990, 1991 SMART 1994 SMART 21. 1B31-1RC-12BR-E-3 1984 OVERLAY 1986 RESURFACE 1986 Baseline 19887, 1990, 1991 PSCAN 1994 SMART 22. 1B31-1RC-12BR-E-4 1991 OVERLAY 1991 Baseline SMART 1994 SMART SMART EXAM 23. 1B31-1RC-12BR-E-5 1991 OVERLAY 1991 Baseline Manual 1994 Manual VOL 24. 1B31-1RC-22AM-1 1982 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 Manual 1994 Manual Manual 25. 1B31-1RC-22AM-4 1982 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 Manual 1994 Manual Manual 26. 1B31-1RC-22BM-1 1982 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 Manual 1993 Manual 1994 Manual 27. 1B31-1RC-22BM-4 1982 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 Manual 1993 Manual 1994 Manual SMART EXAM VOL FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 37 of 46 Rev.1.0 TABLE 7 GL 88-01 CATEGORY E WELD OVERLAYS WITH EFFECTIVE HWC 10% Sample After Two Qualified Weld Examinations (5 welds) Second Interval Volumetric Exams PERIOD 1 PERIOD 2 VIP-075 APPROVED PERIOD 3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 28. 1B31-1RC-28A-2 1990 OVERLAY 1990 Baseline Manual 1994 SMART SMART EXAM 29. 1B31-1RC-28A-4 1990 OVERLAY 1990 Baseline 1991 SMART 1993 SMART 1994 SMART 30. 1B31-1RC-28A-6 1990 OVERLAY 1990 Baseline SMART 1991 PSCAN 1994 SMART SMART EXAM 31. 1B31-1RC-28A-7 1990 OVERLAY 1990 Baseline SMART 1991 SMART 1994 SMART SMART EXAM 32. 1B31-1RC-28A-8 1990 OVERLAY 1990 Baseline SMART 1991 SMART 1994 SMART SMART EXAM 33. 1B31-1RC-28A-10 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 Manual 1994 Manual Manual 34. 1B31-1RC-28A-12 1986 OVERLAY 1986 Baseline 1987, 1990, 1991 PSCAN 1994 SMART SMART EXAM 35. 1B31-1RC-28A-14 1990 OVERLAY 1990 Baseline SMART 1991 SMART 1994 SMART SMART EXAM 36. 1B31-1RC-28B-2 1991 OVERLAY 1991 Baseline PSCAN 1994 SMART

SMART EXAM FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 38 of 46 Rev.1.0 TABLE 7 GL 88-01 CATEGORY E WELD OVERLAYS WITH EFFECTIVE HWC 10% Sample After Two Qualified Weld Examinations (5 welds) Second Interval Volumetric Exams PERIOD 1 PERIOD 2 VIP-075 APPROVED PERIOD 3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 37. 1B31-1RC-28B-3 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 PSCAN 1993 SMART 1994 SMART 38. 1B31-1RC-28B-4 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 PSCAN 1994 SMART 39. 1B31-1RC-28B-8 1990 OVERLAY 1990 Baseline SMART 1994 SMART SMART EXAM 40. 1B31-1RC-28B-9 1990 OVERLAY 1990 Baseline SMART 1991 PSCAN 1994 SMART SMART EXAM 41. 1B31-1RC-28B-10 1990 OVERLAY 1990 Baseline Manual 1991 SMART 1993 SMART 1994 SMART 42. 1B31-1RC-28B-11 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1988, 1990, 1991 Manual 1993 Manual 1994 Manual 43. 1B31-1RC-28B-13 1990 OVERLAY 1990 Baseline SMART 1991 PSCAN 1994 SMART SMART EXAM 44. 1B31-1RC-28B-14 1990 OVERLAY 1990 Baseline SMART 1991 PSCAN 1994 SMART SMART EXAM FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 39 of 46 Rev.1.0 TABLE 7 GL 88-01 CATEGORY E WELD OVERLAYS WITH EFFECTIVE HWC 10% Sample After Two Qualified Weld Examinations (5 welds) Second Interval Volumetric Exams PERIOD 1 PERIOD 2 VIP-075 APPROVED PERIOD 3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 45. 1B31-1RC-28B-15 1990 OVERLAY 1990 Baseline SMART 1991 SMART 1993 SMART 1994 SMART 46. 1B31-1RC-28B-16 1986 OVERLAY 1986 Baseline 1987, 1990, 1991 SMART 1994 SMART 47. 1G31-1RWCUM-6-D-1 1988 PRE-EMPTIVE OVERLAY 1988 Baseline 1991 Manual 1994 Manual 48. 1G31-1RWCUM-6-D-9 1988 PRE-EMPTIVE OVERLAY 1988 Baseline 1991 Manual Manual Weld examination satisfied the requirement for two "qualified" examinations prior to using the VIP-75 reduced examination scop

e. Weld examination credited for 3 rd Interval Weld examination credited for 4 th Interval

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 40 of 46 Rev.1.0 TABLE 8 GL 88-01 CATEGORY E WELD OVERLAYS WITHOUT EFFECTIVE HWC 25 % Sample After Two Qualified Weld Examination (2 welds) Second Interval Volumetric Exams PERIOD 1 PERIOD 2 VIP-075 APPROVED PERIOD 3 3/1/1 1R16 3/96 3/1/2 1R17 9/97 3/1/3 1R18 3/99 3/2/1 1R19 9/00 3/2/2 1R20 3/02 3/3/1 1R21 2/04 3/3/2 1R22 2/06 4/1/1 1R22 2/06 1. 1E11-1RHR-20B-D-3 1982 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 PSCAN 1993 SMART 1994 SMART 2. 1E11-1RHR-20B-D-4 1991 OVERLAY 1991 Baseline PSCAN 1993 SMART 1994 SMART SMART EXAM 3. 1E11-1RHR-20B-D-5 1991 OVERLAY 1991 Baseline PSCAN 1993 SMART 1994 SMART VOL 4. 1E11-1RHR-24A-R-13 1984 OVERLAY 1986 RESURFACE 1986 Baseline 1987, 1990, 1991 PSCAN 1994 SMART VOL 5. 1E11-1RHR-24B-R-12 1986 OVERLAY 1986 Baseline 1987, 1990, 1991 SMART 1993 SMART 1994 SMART 6. 1E11-1RHR-24B-R-13 1982 OVERLAY 1986 RESURFACE 1986 Baseline 1988, 1990, 1991 SMART 1993 SMART 1994 SMART Weld examination satisfied the requirement for a "qualified" examination prior to using the VIP-75 reduced examination scope. Weld examination credited for 3 rd Interval Weld examination credited for 4 th Interval FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 41 of 46 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-1, 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.

Those examinations performed after November 22, 2002 (the Appendix VIII implementation date for dissimilar metal weld s) used qualified procedures. For those examinations performed prior to the dissimilar metal weld Appendix VIII implementation date, it is the position 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 provi ded 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".

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 42 of 46 Rev.1.0 Procedures used prior to Appendix VIII implementation considered as "qualified" 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. 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 UT-HAT-225DV2, "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 procedure was used in 1997 and meets the

BWRVIP-075 intent for a "qualified" procedure.

d. 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.

e. 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.

f. 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.

g. GE Procedure ES-MISN-H-409, Version 1 used after November 22, 2002 (the Appendix VIII implementation date for dissimilar metal welds).

Similar Metal Welds - For similar metal welds, those examinations performed after November 22, 2002 (the Appendix VIII implementation date for austenitic piping welds) by definition used qualified procedures. For those examinations performed prior to the Appendix VIII implementation date, it is the position for HNP-1 that the NDE techniques (personnel and procedures) used from 1988 until the implementation of Appendix VIII are considered acceptable for the detection of IGSCC. (Note: Since each similar metal weld has received at least one examination since 1990, exams performed from 1990 until November 22, 2002 were used in this evaluation).

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 43 of 46 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 eff ective 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-1 will follow the guidance in BWRVIP-62 for an effective HWC program in regards to piping and vessel internals inspection relief.

HNP-1 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-1 periodically injects noble me tal and continuously injects a reduced level of hydrogen.

It should be noted that while HNP-1 has effective HWC, each weld may or may not have effective HWC because of its 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 1-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. 1 Hatch 1 Basis Doc-VIP75.doc Page 44 of 46 Rev.1.0 APPENDIX C DETERMINATION OF "EFFECTIVE" STRESS IMPROVEMENT Processes used at HNP-1 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 screened by Martin B. Sims in Southern Company Generation and Energy Marketing Power Engineering - Metallurgy

& Material Applications.

Per E-Mail dated April 12, 2005 it wa s stated that, "Here is the li st of welds that can not be justified as having "effective stress improvement" based on the BWRVIP-61 recommendations. These welds have some level of improvement over their original

condition that is typically supported by finite element analysis, but may not be considered as fully effective per BWRVIP-61 without some supporting residual stre ss data such as was performed by EPRI for other weld configurations."

This list of welds as shown below was sent to Structural Integrity Associates (SIA) for further evaluation. Preliminary results from SIA indicated that sufficient compressive forces were achieved as required.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 45 of 46 Rev.1.0 Weld Configuration Comments 1B31-1RC-4A-1A Weldolet To Cap Heated zone width not met on cap side of weld. 1B31-1RC-4B-10A Weldolet To Cap Heated zone width not met on cap side of weld. 1B31-1RC-12AR-F-1 Sweepolet To Pipe Heated zone width not met on sweepolet side of weld. 1B31-1RC-12AR-G-1 Sweepolet To Pipe Heated zone width not met on sweepolet side of weld. 1B31-1RC-12AR-H-1 Reducer To Pipe Heated zone width not met on reducer side of weld. 1B31-1RC-12AR-J-1 Sweepolet To Pipe Heated zone width not met on sweepolet side of weld. 1B31-1RC-12AR-K-1 Sweepolet To Pipe Heated zone width not met on sweepolet side of weld. 1B31-1RC-12BR-A-1 Sweepolet To Pipe Heated zone width not met on sweepolet side of weld. 1B31-1RC-12BR-B-1 Sweepolet To Pipe Heated zone width not met on sweepolet side of weld. 1B31-1RC-12BR-C-1 Reducer To Pipe Heated zone width not met on reducer side of weld. 1B31-1RC-12BR-D-1 Sweepolet To Pipe Heated zone width not met on sweepolet side of weld. 1B31-1RC-12BR-E-1 Sweepolet To Pipe Heated zone width not met on sweepolet side of weld. 1B31-1RC-22AM-1BC-1 Run Pipe To Sweepolet No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-22AM-1BC-2 Run Pipe To Sweepolet No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-22AM-2 Cross To Pipe Heated zone width not met on cross side of weld. 1B31-1RC-22AM-3 Cross To Pipe Heated zone width not met on cross side of weld. 1B31-1RC-22AM-3BC-1 Run Pipe To Sweepolet No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-22AM-3BC-2 Run Pipe To Sweepolet No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-22BM-1BC-1 Run Pipe To Sweepolet No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-22BM-1BC-2 Run Pipe To Sweepolet No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-22BM-2 Cross To Pipe Heated zone width not met on cross side of weld. 1B31-1RC-22BM-3 Cross To Pipe Heated zone width not met on cross side of weld. 1B31-1RC-22BM-3BC-1 Run Pipe To Sweepolet No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-22BM-3BC-2 Run Pipe To Sweepolet No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-28A-3 Pipe To Elbow Heated zone offset to elbow side of weld, heated zone width not met on pipe side of weld. 1B31-1RC-28A-9 Pipe To Elbow Heated zone offset to elbow side of weld, heated zone width not met on pipe side of weld. 1B31-1RC-28A-11BC Weldolet To Run Pipe No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-28A-14BC-1 Weldolet To Run Pipe No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1B31-1RC-28B-7 Pipe To Elbow Heated zone offset to elbow side of weld, heated zone width not met on pipe side of weld. 1B31-1RC-28B-12BC Weldolet To Run Pipe No test data to show effective IHSI can be achieved for BC fitting to run pipe welds, minimum heating time not met. 1B31-1RC-28B-15BC-1 Weldolet To Run Pipe No test data to show effective IHSI can be achieved for BC fitting to run pipe welds.

FOURTH INTERVAL VIP-75 AUGMENTED PLAN HATCH UNIT NO. 1 Hatch 1 Basis Doc-VIP75.doc Page 46 of 46 Rev.1.0 Weld Configuration Comments 1B31-1RC-28B-18 Cross To Reducer Heated zone width not met on reducer side of weld.) 1E11-1RHR-20B-D-1 Tee To Pipe Heated zone offset to pipe side of weld, IHSI not effective for tee side. 1E11-1RHR-20B-D-1BC Sweepolet To Run Pipe No test data to show effective IHSI can be achieved for BC fitting to run pipe welds. 1E11-1RHR-24A-R-14 Pipe To Tee Heated zone offset to pipe side of weld, IHSI not effective for tee side. 1E11-1RHR-24B-R-14 Pipe To Tee Heated zone offset to pipe side of weld, IHSI not effective for tee side.

Revision:

1 HNP-1 Fourth Interval VIP-075 Augmented Plan (OL-I) Southern Nuclear Operating Company Period I Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case OL-I HI 1831 -1 RC-12AR-F-2 A-18 IS1 Table 7 1 831 -1 RC-12AR-F-2 84 OVERLAY - 86 RESURFACE AUG 1 831 OWN PRE OL-I HI 1831-1 RC-12AR-F-3 A-18 IS1 Table 7 1831 -1 RC-12AR-F-3 84 OVERLAY - 86 RESURFACE AUG 1 831 OWN PRE OL-I HI 1831 -1 RC-12AR-F-4 A-I 8 IS1 Table 7 1 831 -1 RC-12AR-F-4 1986 OVERLAY AUG 1 831 OWN PRE OL-I H1 1831-1 RC-12AR-G-3 A-18 IS1 Table 7 1 831 -1 RC-12AR-G-3 1986 OVERLAY AUG 1 83 1 OWN PRE OL-I HI 1831-IRC-12AR-G-4 A-I 8 IS1 Table 7 1 831 -1 RC-12AR-G-4 1991 OVERLAY AUG 1 831 OWN PRE OL-I HI 1831 -1 RC-12AR-H-2 A-I 8 IS1 Table 7 1 831 -1 RC-12AR-H-2 84 OVERLAY 86 RESURFACE AUG 1 83 1 OWN PRE OL-1 HI 1831-1 RC-12AR-H-3 A-18 IS1 Table 7 1831 -1 RC-12AR-H-3 84 OVERLAY 86 RESURFACE AUG 1 831 OWN PRE OL-1 HI 1831-1 RC-12AR-H-4 A-18 I SI Table 7 1 831 -1 RC-12AR-H-4 1986 OVERLAY AUG 1 831 OWN PRE OL-1 HI 1831 -1 RC-12AR-J-3 A-I 8 IS1 Table 7 1 831 -1 RC-12AR-J-3 84 OVERLAY - 86 RESURFACE AUG 1 831 OWN PRE OL-1 HI 1831 -1 RC-12AR-K-2 A-I 8 IS1 Table 7 1 831 -1 RC-12AR-K-2 84 OVERLAY - 86 RESURFACE AUG 1 831 OWN PRE Page 1 - 6 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval VIP-075 Augmented Plan (OL-I) Southern Nuclear Operating Company Page 2 - 6 2/1/2006 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 OL-I HI 1831-1 RC-12AR-K-3 A-1 8 IS1 Table 7 1 B31-1 RG-12AR-K-3 84 OVERLAY186 RESURF AUG 1 83 1 om PRE OL-I H1 1831-1 RC-12BR-A-4 A-1 9 IS1 Table 7 1831 -1 RG-12BR-A-4 OVERLAY 1991 AUG 1 83 1 OWN PRE OL-I Hl 1831-1 RC-12BR-B-3 A-1 9 IS1 Table 7 1 831 -1 RG-12BR-B-3 ELBOWTO PIPE 1986 OVERLAY AUG 1 B3 1 om PRE OL-I HI 1831-1 RC-12BR-C-2 A-I 9 IS1 Table 7 1831 -1 RC-12BR-C-2 PIPETO EL84OVERLAYl86 RESURF AUG 1 83 1 OWN PRE OL-I HI 1 B31-1 RC-12BR-C-3 ISIIUTINMP-ES-024509 A-1 9 IS1 Table 7 1831-1 RC-12BR-C-3 ELTO PlPE84OVERLAYl86 RESURF AUG 1 83 1 OWN PRE OL-I HI 1831-1 RC-12BR-C-4 A-1 9 IS1 Table 7 1831-1 RC-12BR-C-4 PIPE TO SAFE-END 1986 OVERLAY AUG 1 831 om PRE OL-I HI 1831-1 RC-12BR-C-5 A-1 9 IS1 Table 7 1831 -1 RC-12BR-C-5 SETONOZlHSl1985/1986,1988OVER AUG 1 83 1 OWN PRE OL-I HI 1 B31-1 RC-12BR-D-2 A-I 9 IS1 Table 7 1 B31-1 RC-12BR-D-2 PIPE TO ELBOW 1986 OVERLAY AUG 1 83 1 OWN PRE OL-1 Hl 1831-1 RC-12BR-D-3 A-1 9 IS1 Table 7 1831 -1 RC-l2BR-D-3 ELTO PlPE84OVERLAYl86 RESURF AUG 1 B3 1 OWN PRE OL-1 HI 1 B31-1 RC-12BR-E-2 A-1 9 IS1 Table 7 1831-1 RC-12BR-E-2 PlPETOEL84OVERLAY186RESURF AUG 1 83 1 OWN PRE d Y) 2 2 5 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - S----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - -----------. - - - - - - - - - - - - ------------ - - - - - - - . - - - - ------------ - - - - - - - - - - . - d 2 2 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - (D r- 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . -

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1 HNP-1 Fourth Interval VIP-075 Augmented Plan (OL-1) Southern Nuclear Operating Company Page 3 - 6 2/1/2006 1 Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Cornp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case OL-1 H1 1831 -1 RC-12BR-E-3 A-1 9 IS1 Table 7 1831 -lRC-I 2BR-E-3 ELTO PlPE84OVERLAYl86 RESURF AUG 1 831 ow PRE OL-1 HI 1831 -1 RC-12BR-E-4 A-1 9 IS1 Table 7 1831 -1 RC-12BR-E-4 PlPETOSEIHS185186 OVERLAY1991 AUG 1 831 om PRE OL-1 H1 1831-1 RC-12BR-E-5 ISIIUTINMP-ES-024-501 A-I 9 IS1 Table 7 1831 -1 RC-12BR-E-5 SET0 NOZZLE lHSl85186 OVERLAY 88 AUG 1 83 1 OWN PRE OL-1 H1 1831-1 RC-22AM-1 A-1 6 IS1 Table 7 1831 -1 RC-22AM-1 CAPTO PlPE82OVERLAY186 RESURF AUG 1 83 1 OWN PRE OL-1 HI 1 831 -1 RC-22AM-4 A-1 6 IS1 Table 7 1 831 -1 RC-22AM-4 PlPETOCAP82OVERLAYW6RESURF AUG 1 831 OWN PRE OL-1 HI 1831-1 RC-22BM-1 A-17 IS1 Table 7 1831 -1 RC-22BM-1 CAPTOPlPE82OVERLAYl86RESURF AUG 1 83 1 om PRE OL-1 HI 1831-1 RC-22BM-4 ISllUTINMP-ES-024-509 A-1 7 IS1 Table 7 1 831 -1 RC-22BM-4 PlPETOCAP82OVERLAY186RESURF AUG 1 831 OWN PRE OL-1 HI 1831-1 RC-28A-10 A-1 4 IS1 Table 7 1 831 -1 RC-28A-1 0 84 OVERLAY - 86 RESURFACE AUG 1 831 om PRE OL-1 HI 1 831 -1 RC-28A-12 A-I 48 IS1 Table 7 1831 -1 RC-28A-12 PIPE TO VALVE 1986 OVERLAY AUG 1 831 OWN PRE OL-1 HI 1831-1 RC-28A-14 A-1 48 IS1 Table 7 1 831 -1 RC-28A-I 4 ELTOPIPEIHSI~~I~~

OVERLAY~O AUG 1 831 OWN PRE w V) 2 2 55 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - s----------- - - - - - - . - - - - - .----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - $ c.7 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - . - - - wh 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . . . . - - - - - - - - - - - - - - . - - - . - - .

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1 HNP-1 Fourth Interval VIP-075 Augmented Plan (OL-I) Southern Nuclear Operating Company Period 1 Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD 1 System Scope I Method I Procedure Code Case OL-1 H1 1831 -1 RC-28A-2 A-14 IS1 Table 7 1831 -1 RC-28A-2 SAFE-END TO PIPE OVERLAY, 1990 AUG 1 831 OWN PRE OL-1 H1 1 831 -1 RC-28A-4 A-14 IS1 Table 7 1831 -1 RC-28A-4 ELBOW TO PIPE OVERLAY 1990 AUG 1 831 OWN PRE OL-1 H1 1 831 -1 RC-28A-6 A-14 IS1 Table 7 1 B31-1 RC-28A-6 PIPE TO ELBOW OVERLAY 1990 AUG 1 83 1 OWN PRE OL-1 HI 1 831 -1 RC-28A-7 A-14 IS1 Table 7 1831 -1 RC-28A-7 EL TO VALVE lHSl85186 OVERLAY 90 AUG 1 83 1 OWN PRE OL-1 HI 1831-1 RC-28A-8 A-14 IS1 Table 7 1831 -1 RC-28A-8 VALVE TO PIPE lHSl85186 OVERLAY 90 AUG 1 831 OWN PRE OL-1 HI 1831-1 RC-28B-10 A-15 IS1 Table 7 1831 -1 RC-288-10 PIPE TO EL lHSl85186 OVERLAY 90 AUG 1 83 1 OWN PRE OL-1 H1 1831-1 RC-28B-11 A-15 IS1 Table 7 1 831 -1 RC-28B-11 EL TO PUMP 84 OVERLAY186 RESURF AUG 1 83 1 OWN PRE OL-1 HI 1831-1 RC-28B-13 A-158 IS1 Table 7 1 831 -1 RC-28B-13 PIPE TO VLV lHSl85186 OVERLAY 90 AUG 1 831 OWN PRE OL-1 HI 1831-1 RC-286-14 A-158 IS1 Table 7 1831 -1 RC-28B-14 1990 OVERLAY AUG 1 831 OWN PRE OL-1 H1 1831-1 RC-28B-15 A-158 IS1 Table 7 1831 -1 RC-28B-15 EL TO PIPE IHSI 85/86 OVERLAY 90 AUG 1 83 1 OWN PRE Page 4 - 6 2/1/2006 ( Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval VIP-075 Augmented Plan (OL-I) 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 OL-1 HI 1831-1RC-28B-16 A-1 58 IS1 Table 7 1831 -1 RC-28B-16 PIPE TO TEE 1986 OVERLAY AUG 1 83 1 OWN PRE OL-1 HI 1831-1 RC-28B-2 A-1 5 IS1 Table 7 1831 -1 RC-288-2 SE TO PIPE IHSI 85186 OVERLAY 91 AUG 1 831 OWN PRE 0 L-I H1 1531-1 RC-28B-3 A-1 5 IS1 Table 7 1831 -1 RC-28B-3 PIPE TO EL 84 OVERLAY186 RESURF AUG 1 83 1 OWN PRE OL-1 HI 1831-1 RC-28B-4 A-1 5 IS1 Table 7 1 831 -1 RC-28B-4 EL TO PIPE 84 OVERLAY186 RESURF AUG 1 83 1 OWN PRE OL-1 HI 1831-1 RC-28B-8 A-1 5 IS1 Table 7 1 831 -1 RC-28B-8 EL TO VALVE OVERLAY 1990 AUG 1 83 1 OWN PRE OL-1 H1 1831-1 RC-28B-9 A-1 5 IS1 Table 7 1831 -1 RC-28B-9 VALVE TO PIPE IHSI 85/86 OVERLAY 90 AUG 1 831 OWN PRE OL-1 HI 1 El 1-1 RHR-20B-D-3 A-23 IS1 Table 8 1 El 1-1 RHR-20B-D-3 82 OVERLAY - 86 RESURFACE AUG 1 El 1 OWN PRE OL-1 HI 1 El 1-1RHR-20B-D-4 A-23 IS1 Table 8 I El 1-IRHR-20B-D-4 1991 OVERLAY AUG 1 El 1 OWN PRE OL-1 HI 1 El 1-1 RHR-20B-D-5 A-23 IS1 Table 8 1 El 1-1 RHR-20B-D-5 1991 OVERLAY AUG 1 El 1 OWN PRE OL-I HI 1E11-1 RHR-24A-R-13 ISllUTINMP-ES-024-509 A-21 IS1 Table 8 1 El 1-1 RHR-24A-R-13 1984 OVERLAY 1986 RESURFACE AUG 1 OWN PRE Page 5 - 6 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval VIP-075 Augmented Plan (OL-I) Southern Nuclear Operating Company Page 6 - 6 2/1/2006 ( Period 1 Period 2 Period 3 wh 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - Category, lso No. IternNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case OL-1 HI 1El1-1 RHR-24B-R-12 A-22 IS1 Table 8 1 El 1-1 RHR-24B-R-12 1986 OVERLAY AUG 1 OWN PRE OL-1 HI 1 El 1-1 RHR-24B-R-13 A-22 IS1 Table 8 1 El 1-1 RHR-24B-R-13 1991 OVERLAY AUG 1 83 1 om pRE OL-1 HI 1G31-1 RWCU-6-D-1 A-32 IS1 Table 7 1 G31-1 RWCU-6-D-1 1988 OVERLAY AUG 1 G31 om PRE OL-1 HI 1 G31-1 RWCUM-6-D-9 A-32 IS1 Table 7 1G31-1 RWCUM-6-D-9 1988 OVERLAY AUG 1 G31 OWN PRE 4 p) 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - w Y) 2 2 5 5 ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - . - ------------ . . - - - - - - - - - -

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1 HNP-1 Fourth Interval VIP-075 Augmented Plan (XB-F) Page 2 - 2 21112006 / Southern Nuclear Operating Company Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope 1 Method I Procedure Code Case XB-F H1 1831 -1 RC-4JP-A-1 A-39 IS1 Table 3 1 831 -1 RC-4JP-A-1 N8A NOZZLE TO SE MSlP 1993 AUG 1 831 OWN PRE XB-F HI 1831-1 RC-4JP-B-1 A-39 IS1 Table 3 1 831 -1 RC-4JP-B-1 N8B NOZZLE TO SE MSlP 1993 AUG 1 831 OWN PRE XB-F HI 1 C11-1 CRD-3-R-18A A-1 IS1 Table 3 lC11-1CRD-3-R-18A CAP TO NOZZLE MSlP 1993 AUG 1 C11 OWN PRE XB-F HI 1E11-1RHR-24A-R-12 A-21 IS1 Table 3 1 El 1-1 RHR-24A-R-12 VALVE TO PIPE lHSl 198511 986 AUG 1 El 1 OWN PRE XB-F HI 1 E21-1 CS-10A-18A A-26, 1 -BF-5 IS1 Table 3 1 E21-1 CS-1 OA-18A PIPE TO SE EXTENSION MSlP 1993 AUG 1 E21 OWN PRE XB-F HI 1 E21-1 CS-10A-20A A-26, 1 -BF-5 IS1 Table 3 1 E21-1 CS-10A-20A SE TO NOZZLE MSlP 1993 AUG 1 E21 OWN PRE XB-F HI 1 E21-1 CS-1 OB-19A A-27, 1 -BF-5 IS1 Table 3 1 E21-1 CS-10B-19A PIPE TO SE EXTENSION MSlP 1993 AUG 1 E21 OWN PRE XB-F HI 1 E21-1 CS-108-21A A-27, 1 -BF-5 IS1 Table 3 1 E21-1 CS-108-21A SE TO NOZZLE MSlP 1993 AUG 1 E21 OWN

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1 HNP-1 Fourth Interval VIP-075 Augmented Plan (XBJ) Southern Nuclear Operating Company Page 2 - 9 112612006 1 Period 1 Period 2 Period 3 (D r. 8! 2 5 5 ----- - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - . - - - - - - - - - - - - - - - + - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary I CornplD I System Scope I Method I Procedure Code Case XB J H1 1831-1 RC-12BR-A-2 A-1 9 IS1 Table 6 1 831 -1 RC-12BR-A-2 PIPE TO ELBOW IHSI 198511986 RO AUG 1 83 1 om PRE XB J HI 1831-1 RC-12BR-A-3 A-1 9 IS1 Table 6 1831-1 RC-12BR-A-3 ELBOWTO PIPE lHSl 198511986 RO AUG 1 831 om PRE XB J HI 1831-1 RC-12BR-B-1 A-1 9 IS1 Table 6 1 831 -1 RC-1 2BR-B-1 B-C TO PIPE IHSl 198511986 RO AUG 1 B3 1 om PRE XB J HI 1 B31-1 RC-12BR-B-2 A-1 9 IS1 Table 6 1831 -1 RC-12BR-B-2 PIPE TO ELBOW lHSl 198511 986 RO AUG 1 831 om PRE XB J Hl 1831-1 RC-12BR-B-4 A-1 9 IS1 Table 6 1831-1 RC-12BR-B-4 PIPET0 SAFE-END lHSl 198511986 RO AUG 1 831 om PRE XB J HI 1831-1 RC-12BR-C-1 A-1 9 IS1 Table 6 1 831 -1 RC-12BR-C-1 REDUCERTO PIPE lHSl198511986 RO AUG 1 83 1 om PRE XB J HI 1831-1 RC-12BR-D-1 A-1 9 IS1 Table 6 1831 -1 RC-12BR-D-1 B-C TO PIPE lHSl 198511986 RO AUG 1 B31 om PRE XB J HI 1831-1 RC-12BR-D-4 A-1 9 IS1 Table 6 1831-1 RC-12BR-D-4 PIPET0 SAFE-END lHSl 198511986 RO AUG 1 831 OWN PRE XB-J H1 1831 -1 RC-12BR-E-1 A-1 9 IS1 Table 6 1831 -1 RC-12BR-E-1 B-C TO PIPE lHSl 198511986 RO AIJG 1 831 OWN PRE XB J HI 1831-1 RC-22AM-1 BC-1 A-1 6 IS1 XB9.31 1831 -1 RC-22AM-1 BC-1 PIPE TO B-C lHSl 198511986 RO AUG 1 831 om PRE 2 c.7 I 5 F ------- - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - d V) 2 2 5 5 ------------ - - - - - - - - ------------ - - - - . - - - - - - - ------------ - - - - --------- - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ . - - - - - - - - - - - -----..----- - - - - - - - - - - - - ------------ - - - - . - - - - - - - .----------- - . . - - - - - - - . -

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1 Category, ItemNO, HNP-1 Fourth Interval VIP-075 Augmented Plan (XB J) Southern Nuclear Operating Company Period 1 Iso No. Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case XB J HI 1 831 -1 RC-22AM-1 BC-2 A-16 IS1 PIPE TO B-C lHSl 198511966 RO AUG OWN PRE XB J HI 1831 -1 RC-22AM-2 A-16 IS1 Table 6 1 831-1 RC-22AM-2 1 83 1 PIPE TO CROSS lHSl198511986 RO AUG OWN PRE - XB J H 1 1 831 -1 RC-22AM-3 A-16 IS1 Table 6 1 831 -1 RC-22AM-3 CROSS TO PIPE lHSl 198511966 RO AUG 1 B3 1 OWN PRE XB-J H1 1031-1 RC-22AM-3BC-1 A-16 IS1 XB9.31 1 831 -1 RC-22AM-3BC-1 PIPE TO B-C lHSl 198511966 RO AUG 1 831 OWN PRE XB J H1 1831-1 RC-22AM-3BC-2 A-16 IS1 XB9.31 1831 -1 RC-22AM-3BC-2 PIPE TO B-C lHSl 198511966 RO AUG 1 831 OWN PRE XB J H1 1831-1 RC-22BM-1 BC-1 A-17 IS1 XB9.31 1831-1 RC-22BM-1 BC-1 PIPE TO B-C lHSl 198511966 RO AUG 1 831 OWN PRE XB J HI 1831 -1 RC-22BM-1 BC-2 A-17 IS1 XB9.31 1831 -1 RC-22BM-1 BC-2 PIPE TO B-C lHSl 198511986 RO AUG 1 83 1 OWN PRE XB J H1 1831-1 RC-22BM-2 A-17 IS1 Table 6 1 831 -1 RC-22BM-2 PIPE TO CROSS lHSl 198511966 RO AUG 1 83 1 OWN PRE XB-J HI 1831 -1 RC-22BM-3 A-17 IS1 Table 6 1831-1 RC-22BM-3 CROSS TO PIPE lHSl 198511966 RO AUG 1 83 1 OWN PRE - XB-J HI 1831 -1 RC-22BM-3BC-1 A-17 IS1 XB9 31 1831 -1 RC-22BM-3BC-1 PIPE TO B-C lHSl 198511966 RO AUG 1 831 OWN PRE Page 3 - 9 Period 2 Period 3 Revision:

1 Page 4 - 9 HNP-1 Fourth Interval VIP-075 Augmented Plan (XB J) Period 2 Southern Nuclear Operating Company Category, Iso No. ItemNO, Cornp. Desc. Class Summary 1 CornplD 1 System Scope I Method 1 Procedure Code Case XB J HI 1831-1 RC-22BM-3BC-2 A-17 IS1 XB9.31 1831 -1 RC-22BM-3BC-2 PIPE TO B-C lHSl198511986 RO AUG 1 831 om PRE XB J HI 1831-1 RC-28A-11 A-146 IS1 Table 6 1831-1 RC-28A-11 PUMP TO PIPE lHSl 198511986 RO AUG 1 831 OWN PRE XB J HI 1831 -1 RC-28A-11 BC A-148 IS1 XB9.31 1831 -1 RC-28A-11 BC PIPE TO BC lHSl 198511986 RO AUG 1 831 om PRE XB 4 HI 1831-1 RC-28A-13 A-I 48 IS1 Table 6 1831 -1 RC-28A-13 VALVETO ELBOW lHSl198511986 RO AUG 1 831 om PRE XB-J HI 1631 -1 RC-28A-14BC A-140 IS1 XB9.31 1031 -1 RC-28A-14BC PIPE TO BC lHSl 198511986 RO AUG 1 831 OWN PRE XB J HI 1831 -1 RC-28A-15 A-148 IS1 Table 6 1831 -1 RC-28A-15 PIPE TO TEE lHSl 198511986 RO AUG 1 831 OWN PRE XB J H1 1831-1 RC-28A-16 A-I 40 IS1 Table 6 1 831 -1 RC-28A-1 6 TEE TO CROSS lHSl198511986 RO AUG 1 83 1 OWN PRE XB J HI 1831 -1 RC-28A-17 A-148 IS1 Table 6 1831 -1 RC-28A-17 CROSS TO REDUCER lHSl198511986 RO AUG 1 831 OWN PRE XB J HI 1831-1 RC-28A-3 A-14 IS1 Table 6 1831 -1 RC-28A-3 PIPE TO ELBOW lHSl 198511986 RO AUG 1 831 OWN PRE XB J H1 1831-1 RC-28A-5 A-14 IS1 Table 6 1831 -1 RC-28A-5 PIPE TO PIPE lHSl 198511986 RO AUG 1 831 OWN PRE Period 3 Period 1 z c, 2 2 z 5 ---- - - - - ---- - - - - - - - - - - - - - - - - - - - - ---- - - - - ---- - - - - - - - - - - - - ---- - - - - ---- - - - - - - - - - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - ---- - - - - - - - - - - - - .--- - - - - ---- - - - - ---- - - - - - - - - - - - -

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1 HNP-1 Fourth Interval VIP-075 Augmented Plan (XBJ) Southern Nuclear Operating Company Period 1 Period 2 Period 3 Category, ItemNO, Iso No. Comp. Desc. Class Summary 1 ComplD I System Scope 1 Method I Procedure Code Case XB J HI 1 831 -1 RC-28A-SA A-14 IS1 Table 6 1 831 -1 RC-28A-5A PIPE TO PIPE lHSi 1985/1986 RO AUG 1 831 OWN PRE XB J HI 1 831-1 RC-28A-8BC A-14 IS1 XB9.31 1 831 -1 RC-28A-8BC PIPE TO BC AUG 1 831 OWN PRE XB J H1 1831-1 RC-28A-9 A-14 IS1 Table 6 1 831 -1 RC-28A-9 1 831 PIPE TO ELBOW lHSl 196511986 RO AUG OWN PRE XB J H1 1831-1 RC-28B-12 A-15B IS1 Table 6 1831 -1 RC-28B-12 1 831 PUMP TO PIPE lHSl 198511 986 RO AUG OWN PRE XB J HI 1 831 -1 RC-28B-12BC A-158 IS1 XB9.31 1 831 -1 RC-28B-12BC PIPE TO BC lHSl 198511986 RO AUG 1 831 OWN PRE XB J H1 1831-1 RC-28B-15BC A-158 IS1 XB9.31 1831 -1 RC-28B-15BC PIPE TO BC lHSl 196511986 RO AUG 1 831 OWN PRE . . .- XB J H1 1831-1 RC-28B-17 A-158 IS1 Table 6 1 831 -1 RC-28B-17 TEE TO CROSS lHSl198511986 RO AUG 1 831 OWN PRE XB J H1 1831-1 RC-28B-18 A-I 58 IS1 Table 6 1 831 -1 RC-28B-18 CROSS TO REDUCER lHSl 198511966 RO AUG 1 831 OWN PRE XB-J H1 1831 -1 RC-28B-5 A-15 IS1 Table 6 1831-1 RC-28B-5 PIPE TO TEE lHSl 198511986 RO AUG 1 831 OWN PRE XB J Hl 1 831 -1 RC-28B-6 A-15 ISI Table 6 1831-1 RC-288-6 TEE TO PIPE lHSl 196511986 RO AUG 1 B31 OWN PRE Revision:

1 HNP-1 Fourth Interval VIP-075 Augmented Plan (XB J) Page 6 - 9 112612006 1 Southern Nuclear Operating Company Period 1 Period 2 Period 3 Category, Iso No. ItemNO, Cornp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case XB J HI 1831-1 RC-280-7 A-1 5 IS1 Table 6 1831 -1 RC-288-7 PIPE TO ELBOW lHSl198511986 RO AUG 1 831 OWN PRE XB J HI 1831-IRC-288-9BC A-I 5 ISI XB9.31 1 831 -1 RC-288-9BC PIPE TO BRANCH CONNECTION AUG 1 83 1 OWN PRE XB J Hl 1831-1 RC-4A-10A A-148 IS1 Table 5 1831 -1 RC-4A-10A BC TO CAP lHSl 198511 986 RO AUG 1 831 OWN PRE XB-J HI 1831 -1 RC-4A-1A A-I 48 IS1 Table 5 1831-1 RC-4A-I A BC TO CAP lHSl I98511986 RO AUG 1 831 OWN PRE XB J HI 1831-1RC-48-10A A-1 58 IS1 Table 5 1831-1 RC-48-10A BC TO CAP lHSl198511986 RO AUG 1 83 1 OWN PRE XB J HI 1031-1 RC-48-IA A-1 58 IS1 Table 5 1831 -1 RC-48-1A BC TO CAP lHSl 198511986 RO AUG 1 831 OWN PRE XB J HI 1831-IRC-4JP-A-2 A-39 IS1 Table 5 1831 -1 RC-4JP-A-2 MSlP 1993 RO AUG 1 83 1 OWN PRE XB J HI 1 831 -1 RC-4JP-0-2 A-39 IS1 Table 5 1831 -1 RC-4JP-8-2 MSlP 1993 RO AUG 1 83 1 OWN PRE XB J HI 1 El 1-1 RHR-208-D-1 A-23 IS1 Table 6 I El 1-1 RHR-208-D-I TEE TO PIPE lHSl 198511986 RO AUG 1 El 1 OWN PRE XB J HI I El 1-1 RHR-20B-D-1 BC A-23 IS1 XB9.31 1 El 1-1 RHR-206-D-1 BC PIPE TO BC lHSl 198511986 RO AUG 1 El I OWN PRE Revision:

1 HNP-1 Fourth Interval VIP-075 Augmented Plan (XB 4) Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case XB J HI 1 El 1-1 RHR-20B-0-2 A-23 IS1 Table 5 1 El 1-1 RHR-20B-D-2 PIPE TO ELBOW lHSl 198511 986 RO AUG 1 El 1 OWN PRE XB J H1 1 El 1-1 RHR-24A-R-I4 A-2 1 ISI Table 5 1E11-IRHR-24A-R-14 PIPE TO TEE IHSl 198511986 RO AUG 1 El I OWN PRE XB J H1 1El1-1 RHR-24B-R-14 A-22 IS1 XB9.11 1 El 1-1 RHR-240-R-14 PIPE TO TEE lHSl 198511986 RO AUG 1 El 1 OWN PRE XB J HI 1 E21-1 CS-10A-19A ISIIUTINMP-ES-024-501 A-26 IS1 Table 5 1 E21-1 CS-IOA-19A MSlP 1993 RO AUG 1 E21 OWN PRE XB J HI 1 E21-1 CS-IOB-20A A-27, 1 -BF-5 IS1 Table 5 1 E21-1 CS-100-20A MSlP 1993 RO AUG 1 E21 OWN PRE XBJ H1 1 G31-1 RWCU-6-D-15A A-32 IS1 Table 6 1 G31-1 RWCU-6-D-15A VALVE TO PIPE lHSl 1985186 RO AUG 1 G31 OWN PRE XB J H1 I G31-1 RWCU-643-158 A-32 IS1 Table 2 1 G31-1 RWCU-6-D-158 PIPE TO PIPE AUG 1 G31 OWN PRE XB J HI 1 G31-1 RWCU-6-0-15C A-32 IS\ Table 2 1 G31-1 RWCU-6-D-15C PIPE TO FLUED HEAD AUG 1 G31 OWN PRE XB J HI 1 G31-1 RWCUM-6-0-10 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-10 ELBOW TO PIPE MSlP 1993 RO AUG 1 G31 OWN PRE XB J HI 1 G31-1 RWCUM-6-D-10-A A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-10-A PIPE TO PIPE MSIP 1993 RO AUG 1 G31 OWN PRE Period 1 Page 7 - 9 1/26/2006 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval VIP-075 Augmented Plan (XBJ) Page 8 - 9 112612006 ( Southern Nuclear Operating Company Period 1 Period 2 Period 3 (P t. 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - . . - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case XB J H1 1 G31-1 RWCUM-6-D-I 1 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-1 1 PIPE TO ELBOW MSlP 1993 RO AUG 1 G31 om PRE XB-J HI 1 G31-1 RWCUM-6-D-12 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-12 ELBOW TO PIPE MSlP 1993 RO AUG 1 G31 OWN PRE XBJ HI 1 G31-1 RWCUM-6-D-13 A-32 IS1 Table 2 1 G31-1 RWCUM-643-13 PIPE TO ELBOW MSlP 1993 RO AUG 1 G31 om PRE XB-J HI 1 G31-I RWCUM-6-D-14 A-32 ISI Table 2 1 G31-1 RWCUM-6-D-1 4 ELBOW TO VALVE MSlP 1993 RO AUG 1 G31 om PRE XB J H1 1 G31-1 RWCUM-6-D-16 ISIIUTINMP-ES-024-501 A-32 IS1 Table 6 1 G31-1 RWCUM-6-D-16 PENETRATION TO PIPE MSlP 1993 RO AUG 1 G31 om PRE XB J HI 1 G31-1 RWCUM-6-D-17 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-I7 PIPE TO ELBOW MSlP 1993 RO AUG 1 G31 OWN PRE XB-J HI 1G31-1 RWCUM-6-D-18 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-18 ELBOW TO PIPE MSlP 1993 RO AUG 1 G31 om PRE XB-J Hl 1 G31-1 RWCUM-6-D-19 A-32 IS1 Table2 1G31-1RWCUM-6-D-19 PIPE TO ELBOW MSlP 1993 RO AUG 1 G31 OWN PRE XB J HI 1G31-1 RWCUM-6-D-2 IS1 Table2 1G31-IRWCUM-6-D-2 PIPE TO ELBOW MSlP 1993 RO AUG 1 RWCU om PRE XB J H1 1 G31-1 RWCUM-6-D-20 ISIIUTINMP-ES-024-501 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-20 ELBOW TO VALVE MSlP 1993 RO AUG 1 G31 OWN PRE IU fi G P: 5 5 F - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . m 2 2 5 5 ------------ - - - - - - - - - - - - ---..------- - - - - - - - - - - - - ------------ - - - - - - - - . . - - ------------ - - - - - - - - - - - - s----------- - - - - - . - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - s----------- - - - - - - - - - - - .

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1 HNP-1 Fourth Interval VIP-075 Augmented Plan (XB J) Southern Nuclear Operating Company Page 9 - 9 112612006 ( 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 XB J HI 1 G31-1 RWCUM-6-D-3 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-3 ELBOW TO PIPE MSlP 1993 RO AUG 1 G31 om PRE XB J HI 1G31-1RWCUM-6-D-4 A-32 IS1 Table 2 1 G31-I RWCUM-6-D-4 PIPE TO VALVE MSlP 1993 RO AUG 1 G31 OWN PRE XB J HI 1 G31-1 RWCUM-6-D-5 A-32 I SI Table 2 1 G31-1 RWCUM-6-D-5 VALVE TO ELBOW MSlP 1993 RO AUG 1 G31 om PRE XB J HI 1 G31-1 RWCUM-6-D-6 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-6 ELBOW TO PIPE MSlP 1993 RO AuG 1 G31 om pRE XB J HI 1 G31-1 RWCUM-6-D-6-BC-1 A-32 IS1 XB9.32 1 G31-1 RWCUM-6-D-6-BC-1 1993 RO AUG 1 G31 om pRE XB J HI 1 G31-1 RWCUM-6-D-7 A-32 IS1 Table 2 1 G31-1 RWCUM-6-D-7 PIPE TO ELBOW MSlP 1993 RO AUG 1 G31 OWN PRE XBJ HI 1G31-1 RWCUM-6-D-8 A-32 IS1 Table 2 1G31-1 RWCUM-6-D-8 ELBOW TO PIPE MSlP 1993 RO AUG 1 G31 om PRE 5 5 ------------ - - - - - - - - - - - - ------------ - - . - - - - - - - - - ------------ - - - - - - - - - - - - ----------.. - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - 2 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - wb 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 1 of 11 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 Class 1 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 For locations where pipe breaks are not postulated on high energy main steam, feedwater, HPCI (steam), RCIC (steam) and RWCU piping located outside containment augmented examinations are generally required. However, per the December 1972 NRC letter from A. Giambusso to Georgia Power Company, augmented examinations are not required.

Examination of IGSCC Susceptible Welds These examinations were originally performed per NUREG-0313 as modified by Generic Letter 88-01. They are currently performed per BWRVIP-075. See 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 Examination of the Scram Discharge Volume (SDV) piping in accordance with NUREG-0803. 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 Class 2 piping. However, 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 w ith 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-one (EBB, 0.5" thick, schedule 80 carbon steel), welds. The 1974 Code required examination of 100% of welds 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 and 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 FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 2 of 11 Rev. 1 examined during the 40-years. Since the largest header has 18 welds, 50% or nine welds had to be examined during the 40-year life or three welds per 10-year interval. The 1980 Code required a surface examination technique for 0.5" thick piping.

For the 3 rd Interval, a 7.5% sample (3 welds) was examined (volumetric and surface). Examinations are shown in Table 1. This piping is design ated as Category C-803 in Schedule Works. For the 4 th Interval, the same three welds will be re-examined.

TABLE 1 AUGMENTED CRD EXAMINATIONS Component ISI FigureExam I4/P1 I4/P2 I4/P3 1. 1C11-2CRD-8N-SDV-1 B-84 2. 1C11-2CRD-8N-SDV-2 B-84 3. 1C11-2CRD-8N-SDV-2A B-84 4. 1C11-2CRD-8N-SDV-2B B-84 5. 1C11-2CRD-8N-SDV-2C B-84 6. 1C11-2CRD-8N-SDV-3 B-84 7. 1C11-2CRD-8N-SDV-4 B-84 Vol 1R24 8. 1C11-2CRD-8N-SDV-6 B-84 9. 1C11-2CRD-8N-SDV-7 B-84 10. 1C11-2CRD-8N-SDV-8 B-84 11. 1C11-2CRD-8N-SDV-9 B-84 12. 1C11-2CRD-8N-SDV-10 B-84 13. 1C11-2CRD-8N-SDV-11 B-84 Vol 1R23 14. 1C11-2CRD-8N-SDV-12 B-84 Vol 1R26 15. 1C11-2CRD-8N-SDV-13 B-84 16. 1C11-2CRD-8S-SDV-1 B-85 17. 1C11-2CRD-8S-SDV-2 B-85 18. 1C11-2CRD-8S-SDV-2A B-85 19. 1C11-2CRD-8S-SDV-3 B-85 20. 1C11-2CRD-8S-SDV-4 B-85 21. 1C11-2CRD-8S-SDV-5 B-85 22. 1C11-2CRD-8S-SDV-6 B-85 23. 1C11-2CRD-8S-SDV-7 B-85 24. 1C11-2CRD-8S-SDV-8 B-85 25. 1C11-2CRD-8S-SDV-9 B-85 26. 1C11-2CRD-8S-SDV-10 B-85 27. 1C11-2CRD-8S-SDV-11 B-85 28. 1C11-2CRD-8S-SDV-12 B-85 29. 1C11-2CRD-8S-SDV-13 B-85 FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 3 of 11 Rev. 1 Feedwater Nozzles and CRD Return Line 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-1 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-1 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. 1

Hatch Basis Doc Aug Other.doc Page 4 of 11 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-1 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. 1

Hatch Basis Doc Aug Other.doc Page 5 of 11 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-1 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; therefore, GE's selection of 10% of the blend radius and a 10-year examination frequency FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 6 of 11 Rev. 1 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.

Additionally, NUREG-0619 also addressed the examination of the Thermal Mixing Tee where CRD is routed to Feedwater. These examinations are not addressed in GE-NE-523-A71-0594-A; therefore, they will be continued each outage as required by NUREG-0619.

This piping is designated as Category C-0619 in Schedule Works

. 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. 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 ISI Program indicates that the portion of thin-w all, 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 Schedul e 40 (or thinner) piping 6", 8", or 10" in diameter discharge piping in RHR and CS. The following table shows the Class 2 welds in the thin wall scope and defines the welds that do not meet criteria (a) or criteria (b).

There are approximately 65 welds that meet criteria (a) or criteria (b); therefore, at least five welds are required to be examined to meet the 7.5% requirement. Within the required scope, five were examined and the requirements were met. See Table 2 below.

This piping is part of the Category C-F-2 population in Schedule Works

.

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 7 of 11 Rev. 1 Table 2 THIN-WALL PIPING AUGMENTED EXAMINATIONS Weld Fig Exam I4P1I4P2 I4P3Comments 1. 1E11-2RHR-6A-DS-1 B-52 2. 1E11-2RHR-10A-DS-1 B-52 3. 1E11-2RHR-10A-DS-2 B-52 4. 1E11-2RHR-6A-TSP-1 B-63 5. 1E11-2RHR-6A-TSP-2 B-63 6. 1E11-2RHR-6A-TSP-3 B-63 7. 1E11-2RHR-6A-TSP-4 B-63 8. 1E11-2RHR-6A-TSP-5 B-63 9. 1E11-2RHR-6A-TSP-6 B-63 10. 1E11-2RHR-6A-TSP-7 B-63 11. 1E11-2RHR-6A-TSP-8 B-63 12. 1E11-2RHR-6A-TSP-9 B-63 13. 1E11-2RHR-6A-TSP-10 B-63 14. 1E11-2RHR-6A-TSP-11 B-63 15. 1E11-2RHR-6A-TSP-12 B-63 16. 1E11-2RHR-6B-DS-1 B-62 17. 1E11-2RHR-10B-DS-1 B-62 18. 1E11-2RHR-10B-DS-2 B-62 19. 1E11-2RHR-10B-DS-3 B-62 20. 1E11-2RHR-6B-TSP-1 B-65 21. 1E11-2RHR-6B-TSP-2 B-65 22. 1E11-2RHR-6B-TSP-3 B-65 23. 1E11-2RHR-6B-TSP-4 B-65 24. 1E11-2RHR-6B-TSP-5 B-65 25. 1E11-2RHR-6B-TSP-6 B-65 26. 1E11-2RHR-6B-TSP-7 B-65 27. 1E11-2RHR-6B-TSP-8 B-65 1R23 28. 1E11-2RHR-6B-TSP-9 B-65 29. 1E11-2RHR-6B-TSP-10 B-65 30. 1E11-2RHR-8-FPD-1 B-71 1R26 31. 1E11-2RHR-8-FPD-2 B-71 1R26 32. 1E11-2RHR-8-FPD-3 B-71 33. 1E11-2RHR-8-FPD-4 B-71 34. 1E11-2RHR-8-FPD-5 B-71 35. 1E11-2RHR-10A-SWDS-1 B-48 36. 1E11-2RHR-10A-SWDS-2 B-48 37. 1E11-2RHR-10A-SWDS-3 B-48 38. 1E11-2RHR-10A-SWDS-4 B-48 39. 1E11-2RHR-10A-SWDS-5 B-48 1R23 FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 8 of 11 Rev. 1 Table 2 THIN-WALL PIPING AUGMENTED EXAMINATIONS Weld Fig Exam I4P1I4P2 I4P3Comments 40. 1E11-2RHR-10A-SWDS-6 B-48 41. 1E11-2RHR-10A-SWDS-7 B-48 42. 1E11-2RHR-10A-SWDS-8 B-48 43. 1E11-2RHR-10A-SWDS-9 B-48 44. 1E11-2RHR-10A-SWDS-10 B-48 45. 1E11-2RHR-10A-SWDS-11 B-48 46. 1E11-2RHR-10A-SWDS-12 B-48 47. 1E11-2RHR-10B-SWDS-1 B-60 48. 1E11-2RHR-10B-SWDS-2 B-60 49. 1E11-2RHR-10B-SWDS-3 B-60 50. 1E11-2RHR-10B-SWDS-4 B-60 1R25 51. 1E11-2RHR-10B-SWDS-5 B-60 52. 1E11-2RHR-10B-SWDS-6 B-60 53. 1E11-2RHR-10B-SWDS-7 B-60 54. 1E11-2RHR-10B-SWDS-8A B-60 55. 1E11-2RHR-10B-SWDS-9A B-60 56. 1E11-2RHR-10B-SWDS-10 B-60 57. 1E11-2RHR-10B-SWDS-11 B-60 58. 1E11-2RHR-10B-SWDS-12 B-60 59. 1E21-2CS-10A-1 B-6 60. 1E21-2CS-10A-2 B-6 61. 1E21-2CS-10A-3 B-6 62. 1E21-2CS-10B-1 B-9 63. 1E21-2CS-10B-2 B-9 64. 1E21-2CS-10B-3 B-9 65. 1E21-2CS-10B-4 B-9 65 TOTAL WELDS 5 WELDS REQUIRED 2 1 2 1E11-2RHR-6A-RVD-1 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-2 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-3 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-4 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-5 B-69 Isolable (1E11-F055A) - Not ECC FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 9 of 11 Rev. 1 Table 2 THIN-WALL PIPING AUGMENTED EXAMINATIONS Weld Fig Exam I4P1I4P2 I4P3Comments 1E11-2RHR-6A-RVD-6 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-7 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-8 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-9 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-10 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-11 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-12 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-13 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-14 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-15 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-16 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-17 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6A-RVD-18 B-69 Isolable (1E11-F055A) - Not ECC 1E11-2RHR-6B-RVD-1 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-2 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-3 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-4 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-5 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-6 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-7 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-8 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-9 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-10 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-11 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-12 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-13 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-14 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-15 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-16 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-17 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-18 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-19 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-6B-RVD-20 B-73 Isolable (1E11-F055B) - Not ECC 1E11-2RHR-8-FPS-7 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-8 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-9 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-10 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-11 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-12 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-13 B-72 Suction Piping - Not Required

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 10 of 11 Rev. 1 Table 2 THIN-WALL PIPING AUGMENTED EXAMINATIONS Weld Fig Exam I4P1I4P2 I4P3Comments 1E11-2RHR-8-FPS-14 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-15 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-16 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-17 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-18 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-19 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-20 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-21 B-72 Suction Piping - Not Required 1E11-2RHR-8-FPS-22 B-72 Suction Piping - Not Required 1E21-2CS-10A-TL-1 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-2 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-3 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-4 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-5 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-6 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-7 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-8 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-9 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-10 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-11 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-12 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10A-TL-13 B-5 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-1 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-2 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-3 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-4 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-6 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-7 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-8 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-9 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-10 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-11 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-12 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-13 B-8 Isolable Test Line - Not ECC, RHR, or CHR 1E21-2CS-10B-TL-14 B-8 Isolable Test Line - Not ECC, RHR, or CHR

FOURTH INTERVAL AUGMENTED "OTHER" PLAN HATCH UNIT NO. 1

Hatch Basis Doc Aug Other.doc Page 11 of 11 Rev. 1 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.

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. Examinations were chosen on the 6" Suction line (B-88 or B-89) or 10" torus steam discharge line (B-24or B-25).

Revision:

1 HNP-I Fourth Interval Thermal Tee Augmented Plan Southern Nuclear Operating Company Period 1 Category, Iso No. IternNO, Comp. Desc. Class Summary 1 ComplD 1 System Scope 1 Method 1 Procedure Code Case C-0619 HI 1 G31-2RWCU-4-R-3A ISI11 8-83 IS1 1 G31-2RWCU-4R-3A ISIIUTI TEE TO PIPE AUG 2SS G31 IS I11 OWN IS111 PRE C-0619 HI 1 G31-2RWCU-4-R-4C ISIlI 8-83 IS1 1 G31-2RWCU-4-R-4C ISI11 PIPE TO PIPE AUG 2SS G31 IS Ill OWN IS Ill PRE IS Ill IS Ill Page I - I 1/26/2006 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval CRD Header Augmented Plan Page 1 - 3 1/26/2006 ( Southern Nuclear Operating Company Period 1 Period 2 Period 3 wt- 2 2 ,I ,I - - - - --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case C-0803 HI 1 C11-2CRD-8N-SDV-1 6-84 IS1 1 C11-2CRD-8N-SDV-1 CAP TO PIPE AIJG 2s Cll ow pRE C-0803 Hl 1 Cll-2CRD-8N-SDV-10 6-84 IS1 1 C11-2CRD-8N-SDV-10 PIPE TO PIPE AIJG 2s C11 ow PRE C-0803 Hl 1 Cll-2CRD-8N-SDV-11 8-64 ISI 1C11-2CRD-8N-SDV-11 PIPE TO CAP AIJG 2s Cll ow PRE C-0803 HI 1C11-2CRD-8N-SDV-12 6-84 IS1 1 C11-2CRD-8N-SDV-12 TEE TO PIPE AIJG 2s Cll ow pRE C-0803 Hl 1 C11-2CRD-8N-SDV-13 6-84 IS1 1 C1 1 -2CRD-8N-SDV-13 PIPE TO CAP AIJG 2s Cl I ow PRE C-0803 Hl 1 Cll-2CRD-8N-SDV-2 6-84 ISI 1 CI1-2CRD-8N-SDV-2 PIPE TO PIPE AUG 2 S Cll ow PRE C-0803 Hl 1 Cll-2CRD-8N-SDV-2A 6-84 IS1 1 C11-2CRD-8N-SDV-2A PIPE TO PIPE AUG 2s Cll ow PRE C-0803 HI 1Cll-2CRD-8N-SDV-28 8-84 IS1 1 C11-2CRD-8N-SDV-26 PIPE TO PIPE AIJG 2s Cl I ow PRE C-0803 Hl 1Cll-2CRD-8N-SDV-2C 8-84 ISI 1 C11-2CRD-8N-SDV-2C PIPE TO PIPE AIJG 2 S Cll ow PRE C-0803 HI 1 Cll-2CRD-8N-SDV-3 6-84 IS1 1 C11-2CRD-8N-SDV-3 PlPE TO ELBOW AIJG 2 S Cll ow PRE A O-8 2 g 5 F - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - s s KK 5 ,I _-_____----- - - - - --------- - - - - _-_____----- - - - - - - - - - - - - -s---------- - - - - - - - - - - - - - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - -

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Revision:

1 HNP-1 Fourth Interval RClC Class S Welds Augmented Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc.

class Summary I ComplD 1 System Scope I Method I Procedure Code Case CF-R HI 1 E51-2RCIC-10-TD-8A 8-24 IS1 1 E51-2RCIC-1 O-TD-8A ELBOWTO PIPE AUG S E5 1 OWN PRE CF-R HI 1 E51-2RCIC-10-TD-8B 8-24 IS1 1 E51-2RCIC-10-TD-8B PIPE TO ELBOW AUG S E5 1 OWN PRE CF-R HI 1 E51-2RCIC-10-TD-8C 8-24 IS1 ELBOW TO PlPE AUG OWN PRE CF-R HI 1 E51-2RCIC-1 O-TD-8D 8-24 IS1 1 E51-2RCIC-1 O-TD-8D PIPE TO PIPE AUG S E5 1 OWN PRE CF-R HI 1 E51-2RCIC-10-TD-9 8-24 IS1 1 E51-2RCIC-10-TD-9 PIPE TO ELBOW AUG S E5 1 OWN PRE CF-R HI 1 E51-2RCIC-6-PS-1 8-88 IS1 1 E51-2RCIC-6-PS-1 REDUCER TO PIPE AUG S E51 OWN PRE CF-R HI 1 E51-2RCIC-6-PS-10 B-88 IS1 1 E51-2RCIC-6-PS-10 PIPE TO ELBOW AUG S E5 1 OWN PRE CF-R HI 1 E51-2RCIC-6-PS-11 ISIII 8-88 IS1 1 E51-2RCIC-6-PS-11 ELBOWTO PIPE AUG S E5 1 OWN PRE CF-R Hl 1 E51-2RCIC-6-PS-12 ISIII 8-88 IS1 1 E51-2RCIC-6-PS-12 PIPE TO ELBOW AUG S E51 OWN PRE CF-R HI 1 E51-2RCIC-6-PS-13 B-88 IS1 1 E51-2RCIC-6-PS-13 ELBOW TO PIPE AUG S E51 OWN PRE Page 3 - 6 Period 1 Period 2 Period 3

Revision:

1 Category, ItemNO, HNP-1 Fourth Interval RClC Class S Supports Augmented Plan Southern Nuclear Operating Company Iso No. Comp. Desc. Class Summary 1 ComplD I System Scope I Method I Procedure Code Case FA-R HI 1El1-RHRH-265 8-88 IS1 AUG OWN PRE FA-R H1 1 El 1 -RHRH-266 8-88 IS1 1 El 1-RHRH-266 ANCHOR AUG S El I OWN PRE FA-R HI 1E11-RHRH-266A 8-88 IS1 1 El 1-RHRH-266A RESTRAINT AUG S El I OWN PRE FA-R HI 1 El 1-RHRH-267 8-88 IS1 1 El 1-RHRH-267 RESTRAINT AUG S El I OWN PRE FA-R HI 1 E51-RCICH-16 8-88 IS1 1 E51-RCICH-16 SUPPORT AUG S E51 OWN PRE FA-R HI 1 E51-RCICH-702 lSlN 8-89 IS1 1 E51-RCICH-702 RESTRAINT AUG S E5 1 OWN PRE FA-R HI 1 E51-RCSEH-20 lSl// 8-24 IS1 1 E51 -RCSEH-20 SNUBBER AUG S E51 OWN PRE FA-R HI 1E51-RCSEH-21 8-25 IS1 1 E51-RCSEH-21 SNUBBER AUG S E5 1 OWN PRE FA-R HI 1 E51-RCSEH-22 8-25 IS1 1 E51 -RCSEH-22 RESTRAINT AUG S E51 OWN PRE FA-R HI 1 E51-RCSEH-3 8-24 IS1 1 E51-RCSEH-3 RESTRAINT AUG S E51 OWN PRE Page 2 - 4 Period I Period 2 Period 3 Period 3 Revision:

1 HNP-1 Fourth Interval RClC Class S Supports Augmented Plan Page 3 - 4 Southern Nuclear Operating Company Period 2 e UI 2 2 5 5 - - - - - - - - - - - - - - - - - - - - -------- - - - - - - - - S--- -------- - - - - - - - - - - - - -------- - - - - -------- - - - - - - - - -------- - - - - -------- - - - - - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - --- - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD I System Scope I Method I Procedure Code Case FA-R HI 1E51-RCSEH-3A 8-24 IS1 1 E51 -RCSEH-3A SPRING AUG S E5 1 OWN PRE FA-R H1 1 E51-RCSEH-4 8-25 IS1 1 E51-RCSEH-4 RESTRAINT AUG S E51 OWN PRE FA-R HI 1 E51-RCSEH-4A 8-25 IS1 1 E51 -RCSEH-4A SPRING AUG S E5 1 OWN PRE F A-R HI 1 E51 -RCSEH-5 0-25 IS1 1 E51 -RCSEH-5 SPRING AUG S E5 1 OWN PRE FA-R HI 1E51-RCSEH-714 8-24 IS1 1 E51 -RCSEH-714 SPRING AUG S E5 1 OWN PRE FA-R H1 1 E51-RCSEH-715 8-24 IS1 I E51 -RCSEH-715 SNUBBER AUG S E5 1 OWN PRE F A-R HI 1E51-RCSEH-717 8-24 IS1 1 E51 -RCSEH-717 SPRING AUG S E5 1 OWN PRE FA-R HI 1 E51-RCSEH-718 8-24 IS1 1 E51 -RCSEH-718 RESTRAINT AUG S E5 1 OWN PRE FA-R HI 1 E51-RCSEH-719 8-24 IS1 I E51-RCSEH-719 SNUBBER AUG S E5 1 OWN - - - - - - - - PRE - - - - - - - - FA-R HI 1 E51-RCSEH-720 ISI11 8-24 IS1 -------- I E51 -RCSEH-720 SNUBBER AUG - . - - - - - - S E5 1 --.- Period I 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ------ - - - - - - - - - - - . - - - - - - - - - - - - - - - - ----- - - - -

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1 HNP-1 Fourth Interval RClC Class S Supports Augmented Plan Southern Nuclear Operating Company Category, Iso No. ItemNO, Comp. Desc. Class Summary I ComplD I System Scope I Method I Procedure Code Case FA-R HI 1 E51-RCSEH-721 6-25 IS1 SNUBBER AUG OWN PRE Page 4 - 4 1/26/2006 1 Period 1 Period 2 Period 3 Revision:

1 HNP-1 Fourth Interval RClC Class S Welded Attatcments Augmented Plan Page I - I 112612006 ( Southern Nuclear Operating Company Period 1 Period 2 Period 3 w h 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Category, Iso No. ItemNO, Comp. Desc.

Class Summary I ComplD 1 System Scope I Method I Procedure Code Case CC-R H1 1 E51-2RCIC-10-TD-1OPS-1 AND 2 8-24 IS1 1 E51-2RCIC-10-TD-1 OPS-1 AND 2 E51-RCSEH-3 Lug AUG S E5 1 OWN PRE CC-R HI 1 E51-2RCIC-10-TD-12PS-1 8-24 IS1 1 E51-2RCIC-10-TD-12PS-1 E51-RCSEH-719 LUG AUG S E51 ow PRE CC-R HI 1E51-2RCIC-10-TD-14PS-1 THRU 4 8-25 IS1 1 E51-2RCIC-10-TD-14PS-1 THRU 4 E51 -RCSEH-4 AUG S E51 om PRE CC-R H1 1 E51-2RCIC-10-TD-4PL-1 THRU 4 8-24 IS1 1 E51-2RCIC-10-TD-4PL-1 THRU 4 E51 -RCSEH-714 AIJG S E51 om PRE CC-R H1 1 E51-2RCIC-6-PS-13PS-1 THRU 3 8-88 IS1 1 E51-2RCIC-6-PS-13PS-1 THRU 3 El 1-RHRH-263 AUG S E5 1 om PRE CC-R H1 1 E51-2RCIC-6-PS-18PS-1 ISI11 8-88 IS1 1 E51-2RCIC-6-PS-18PS-1 E51 -RCICH-16 AUG S E51 om PRE CC-R H1 1 E51-2RCIC-6-PS-5PS-1 AND 2 8-88 IS1 1 E51-2RCIC-6-PS-SPS-1 AND 2 El 1-RHRH-266 LUG AUG s E51 OWN PRE 2 2 5 5 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - e V) 2 2 5 5 ------------ - - - - - - - - - - - - --------s--- - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - ------------ - - - - - - - - - - - - --------s--- - - - - - - - - - - - - ------------ - - - - - - - - - - - -