ML20137H996

Rev 1 to 10-yr Inservice Insp Program

ML20137H996
Person / Time
Site:	Waterford
Issue date:	11/26/1985
From:	LOUISIANA POWER & LIGHT CO.
To:
Shared Package
ML20137H970	List: ML20137H996 W3P85-3273, Forwards Rev 1 to 10-yr Inservice Insp Program Per 10CFR50.55(g).Changes Include Addl Drawings Establishing Exam Boundaries & Reduction of Bolting Exams from 40 to 20 Due to Deleted Bolting Not Pressure Retaining
References
PROC-851126, W340076E, NUDOCS 8512020527
Download: ML20137H996 (98)

Text

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10 YEAR INSERVICE INSPECTION PROGRAM Rev. I 1.0 GENERAL 1.1 Introduction 1.2 Effective Date 1.3 Records 1.4 Personnel Qualification 1.5 Method of Examination 1.6 Supplemental Program for IGSCC 1.7 Augmented Inservice Inspection Program for High Energy Piping 1.8 Eddy Current Examination of Steam Generator Tubing 1.9 Reactor Coolant Pump Flywheel Examination 1.10 Mechanical and Hydraulic Snubber Examination 1.11 Ultrasonic Calibration Standards 1.12 Subsequent Inservice Inspection Plan Revisions 1.13 Repairs and Replacements 1.14 Additional Examinations O

2.0 INSERVICE INSPECTION OF CLASS 1 COMPONENTS (IWB) 2.1 Exemptions 2.2 System Pressure Tests 2.3 Examination Table and Figures l

3.0 INSERVICE INSPECTION OF CLASS 2 COMPONENTS (IWC) 3.1 Exemptions 3.2 System Pressure Tests 3.3 Examination Table and Figures l

4.0 INSERVICE INSPECTION OF CLASS 3 COMPONENTS (IWD) 4.1 Exemptions 4.2 System Pressure Tests 4.3 Examination Table h2020527 851126 G

ADOCK 05000332 PDR W340076E 1

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g, 10 YEAR INSERVICE INSPECTION PROGRAM Rev. I l

I 5.0 INSERVICE INSPECTION OF SUPPORTS (IWF) 5.1 Examination Table and Figure 6.0 INSERVICE INSPECTION OF PUMPS AND VALVES i

(IWP) (IW) 4 7.0 NELIEF REQUESTS 4

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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 C'\\

U 1.0 GENERAL 1.1 Introduction In accordance with 10CFR50.55a(g) " Inservice Inspection Require-ments", the following is the Inservice Inspection Program for the first 10 Year Interval of commercial operation at the Waterford Nuclear Plant, Unit No. 3.

This program meets, as much as practical, the requirements of the 1980 Edition through Winter 81 addenda of the ASME Boiler and Pressure Vessel Code. This program documents all examination requirements, relief from required examinations and any supplemental examinations applied to plant systems. The examin-ations are scheduled in accordance with Inspection Program B (IWA-2420) and implemented by Outage Plans which contain specific drawings, NDE procedures, calibration standard information, and the minimum / maximum number of items to be examined per period.

V 1.2 Effective Date The start of the first 10 Year Interval commences at placement of Waterford 3 into commercial operation as specified in IWA-2400.

If the unit is out of service continuously for 6 months or more during the Interval, the Inspection Interval may be extended at LP&L's option for a period equivalent to the outage.

1.3 Records Records and documentation of all information and examination results which provide the basis for evaluation and facilitate comparison with results from previous and subsequent inspections are maintained in accordance with IWA-6000 and are available for review for the active life of the plant.

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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 l

1.4 Personnel Qualification Personnel performing nondestructive examinations are qualified with a written procedure prepared in accordance with SNT-TC-1A 1980. The certification of personnel currently qualified with a procedure prepared in accordance with 1975 edition of SNT-TC-1A is valid until recertification is required. At that time, recertification is in accordance with the 1980 edition of SNT-TC-1A.

In addition, the requirements of IWA-2300 apply when certifying NDE personnel.

1.5 Method of Examination The method of examination is specified in Examination Tables in subsequent sections. When determining acceptability of flaw indications, IWA-3000 " Standards for Examination Evaluation" shall be used. Where acceptance standards for a particular component or examination category are in the course of preparation, the evaluation may be based on acceptance standards in later editions of Section XI accepted by the Regulatory Authorities or acceptance standards for materials and welds specified in the Section III edition applicable to the construction of the component. All results of evaluations and examinations are documented in accordance with Article IWA-6000.

Specific techniques for performing examinations are noted as follows:

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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 l

O 1.5.1 Ultrasonic Examination Ultrasonic (UT) examination is performed when a volumetric examination is required. The examinations are performed in accordance with Appendix III of Section XI and Articles IV and V of Section V, as applicable. A documented evaluation of any indications that are 50% of the Distance Amplitude Correction (DAC) Curve or greater is recorded. Any geometric indication 100% of DAC or greater is evaluated by a Level II or III examiner to the extent necessary to determine the size, shape, identity and the location of the reflector. Any non-geometric indication 20% of DAC or greater is recorded and investigated by a Level II or Level III examiner to the extent necessary to 1

determine the shape, identity and location of the reflector.

1.5.2 Radiographic Examination Radiographic (RT) examination is used to supplement ultrasonic examination as required. Procedures used will be as specified in Article 2 of Section V.

I 1.5.3 Magnetic Particle Examinations A

t Magnetic particle (MT) examination is used when surface examination of carbon steel items is required. Procedures used will be as specified in Article 7 of Section V.

Where conditions exist which render MT impossible or impractical, PT is utilized as an alternate surface exam if possible.

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10 YEAR INSERVICE INSPECTION PROGRAM f

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1.5.4 Liquid Penetrant Examinations Liquid penetrant (PT) examination is used when a surface examination is required on non-magnetic items.

Procedures used will be as specified in Article 6 of Section V.

As noted in 1.5.3, PT is also an acceptable alternative for carbon steel items.

1.5.5 Visual Examinations Visual Examination is employed whenever a VT-1, VT-2, VT-3, or VT-4 is required by the Examination Tables in subsequent sections. Procedures used will be in acccedance with IWA-2210.

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1.6 Supplemental Program for Intergranular Stress Corrosion Cracking (IGSCC)

This supplemental program was established by Louisiana Power and t

Light in order to address concerns relative to IGFJC in stainless steel piping containing stagnant borated water.

LP&L selected approximately 10% of the total number of welds in certain designated lines of Safety Injection and Containment Spray systems for volumetric examination in lieu of the required surface examinations.

Every effort has been made to select a representative sample of weld types with particular emphasis placed on areas where structural discontinuities are present. See Relief Request ISI-002 for specific lines that were selected for this program.

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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 l

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1.7 Augmented Inservice Inspection Program for High Energy Piping Based on a review of NUREG 0800 (formerly NUREG-75/087), Sections 6.6 and 3.6.1, including Branch Technical Position ASB 3-1 and Appendicies A through C, and the Waterford 3 FSAR Sections 6.6 and 3.6.2.1.4, LP&L has developed an augmented program for implementation at the Waterford 3 Steam Electric Station. The augmented ISI program is based upon the requirements of paragraph 11.7 of SRP Section 6.6.

These requirements are applied by LP&L as follows:

1.7.1 Main Steam and Feedwater Piping 1.7.1.1 All circumferential and longitudinal welds from both Steam Generators to the first rigid restraint past the outer containment isolation valve are 100 percent 7-s volumetrically examined except as restricted by part

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geometry or access.

1.7.1.2 All welds within the Class 2 boundaries of the Main Steam and Feedwater systems not addressed in 1.7.1.1 above are examined in accordance with the methods specified in Table IWC-2500-1, Category C-F.

1.7.2 Safety Injection Piping 1.7.2.1 The augmented ISI requirements of SRP 6.6 and BTP 3-1 are imposed on the two 14-inch shutdown cooling lines and the four 8-inch LPSI lines penetrating containment.

1.7.2.2 All circumferential welds on the two 14-inch shutdown cooling lines between the containment inboard and outboard isolation valves are 100 percent volumetri-O)

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cally examined except as restricted by part geometry or access.

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10 YEAR INSERVICE INSPECTION PROGRAM l

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1.7.2.3 All circumferential welds on the four 8-inch LPSI lines between the containment inboard and outboard isolation valves are 100 percent volumetrically examined except as restricted by part geometry or access.

1.7.2.4 All remaining welds within the Class 2 examination boundaries of the Safety Injection system are examined by the method specified in Table IWC-2500-1, Category C-F.

1.7.3 The following line numbers are included in the Augmented Program:

LINES IN AUGMENTED PROGRAM 2MS34-1A 2MS40-163A 2MS40-5A 2MS40-164A P SMS40-6A 2MS34-10B 2MS40-165B 2MS40-39B 2MS40-166B P SMS40-15 2W18-40A 2W20-12A P SW20-11 2W18-41B 2W20-14B P SW20-13 P 2SI14-18A W340076E 8

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10 YEAR INSERVICE INSPECTION PROGRAM l

Rev. 1 O

P 2SI14-18B 2SI8-138RL2B 2SI8-130RL2A j

2SI8-113RLIA 2SI8-122RLIB NOTE - The entire line is included in the Augmented Program unless noted by a "P" which denotes partial.

1.8 Eddy Current Examination of Steam Generator Tubing The Steam Generator tubing is examined in accordance with paragraphs 4.4.4.0 through 4.4.4.5 of the Waterford 3 Plant Technical Spec-4 i

ifications and USNRC Regulatory Guide 1.83.

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1.9 Reactor Coolant Pump Flywheel Examination i

t The Reactor Coolant Pump Flywheel examination will be performed in accordance with paragraph 4.4.9 of the Waterford 3 Plant Technical

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Specifications and USNRC Regulatory Guide 1.14.

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1.10 Mechanical and Hydraulic Snubber Examination e

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i All mechanical and hydraulic snubbers are visually examined and I

functionally tested in accordance with paragraph 4.7.8 of the

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Waterford 3 Technical Specifications. Therefore, snubbers are not included in the scope of the Inservice Inspection Program.

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10 YEAR INSERVICE INSPECTION PROGRAM l

Rev. 1

s 1.11 Ultrasonic Calibration Standards Existing PSI calibration standards are used for the first 10 Year Interval at Waterford 3.

These standards were utilized during preservice and were designed and manufactured to satisfy the intent of Article 5 and Appendices I and III of Section XI,1974. Modifi-cation to or replacement of existing calibration standards would not significantly increase meaningful data and could reduce baseline comparison capability.

Any new blocks that are purchased will satisfy the requirements in effect at the time of purchase.

1.12 Subsequent Inservice Inspection Plan Revisions Subsequent 120 month Inspection Intervals throughout the service life of the facility will comply, where practical, with those requirements in editions of the code and addenda in effect 12

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months prior to the start of each Inspection Interval.

1.13 Repairs and Replacements Repairs and replacements at Waterford 3 are performed in accordance with the LP&L Section XI Repair and Replacement Prograu. As required by Articles IWA-4000 and IWA-7000, this program delineates the essential requirements of the complete repair cycle including weld repairs and procurement and installation of replacements.

The program consists of administrative procedures which describe overall departmental responsibilities and interfaces, the Authorized Nuclear Inspector's involvement and documentation requirements.

Also, Maintenance and Quality Control departmental procedures implement controls for special processes essential to the repair program such as flaw removal, weld repair, post weld heat treatment and non-destructive examination.

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1-t 10 YEAR INSERVICE INSPECTION PROGRAM l

Rev. 1 O

The repair program complies with the requirements of Articles IWB, i

IWC, IWD and IWF-4000.

1.14 Additional Examinations i

If examinations conducted.during Inservice Inspection reveal i

indications exceeding allowable standards, additional examinations i

are performed as specified in IWB, IWC and IWF-2430.

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I 10 YEAR INSERVICE INSPECTION PROGRAM l

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O 2.0 INSERVICE INSPECTION OF CLASS 1 COMPONENTS Based on Table IWB-2500-1, the examination categories and items identified in the Examination Table are subject to examination under LP&L's Inservice Inspection Program. The Examination Table identifies the non-exempt components subject to examination, the total number of items under each category, Relief Requests associated with each item, and figure number if applicable. The Examination Table is followed by figures which illustrate and define the inspection boundaries of each item. All welds whose stress levels exceed that shown in IWB-2500-1 (Cat B-J) are examined. Additional details regarding exemptions and hydrostatic testing are addressed below.

2.1 Exemptions (IWB)

The following IWB-1220(B) exemptions apply to all applicable cate-g gories of IWB-2500-1. Also, the selection of supports under

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Subsection IWF is affected by these exemptions.

2.1.1 Piping of 1 inch nominal pipe size and smaller, except for Steam Generator tubing.

2.1.2 Components and their connections in piping of 1 inch nominal pipe size and smaller.

2.2 System Pressure Tests (IWB)

As required by Tables IWA-5210-1 and IWB-2500-1, the system pressure tests described in IWA-5211 are conducted as follows:

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10 YEAR INSERVICE INSPECTION PROGRAM l

Rev. 1 O

2.2.1 Hydrostatic Test (IWA-5211d)

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The hydrostatic testing requirements of IWB-2500 are required to be performed at or near the end of each Inspection Inter-val. The procedures detailing the hydrostatic testing and any Relief Requests associated with these tests will be I

developed during the second period of the first Interval.

All hydrostatic testing required due to repair or replacement activity is handled on a case by case basis. The hydrostatic tests and associated repair / replacement activities are docu-mented on NIS-II forms which are submitted with an Outage Summary Report after refueling outages.

2.2.2 System Leakage Test (IWA-5211a)

Af ter each refueling outage, the Class 1 pressure boundary is i

subjected to a visual exam (VT-2) with the system (s) at I

nominal operating pressure. The pressure retaining boundary corresponds to the Reactor Coolant System boundary with all j

Class 1 valves in the normal position required for normal

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reactor startup. Also, the visual exam (VT-2) extends to and includes the second closed valve at the Class 1 pressure boundary extremity.

2.3 Examination Table and Figures i

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I 10 YEAR INSERVICE Ile5PECTION VI LoutSIANA PONER AND LIGif leATEIIFORD STEAM ELECTRIC STATION tsNIT ND. 3 IteSERVICE INSPECTION Pfl0GRAW FON CL. ASS 1, 2. AND 3 Cop 0 BENTS EXAmiseAEIGN CAffG0ltY 5-A I

tuvAL

[ XA NTIGATIUpt j

ITES IG.

AK AS EXAMIIED PER ITES K il m IIELIEF/rfERRENTS 81.10 Shell Nelds Bl.11 Circumferential 3

volumetric Fig 18 88.12 Longitudinal 9

Volumetric Fig 28 51.20 Head Nelds 81.21 Circumferential 2

Volumetric Fig 38 81.22 Iserldtonal IO Volumetric Fig 38

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81.30 Shell-to-Flange Meld I

volumetric Fig 48 81.40 Head-to-Flange leeld 1

Volumetric & Surface Fig 58 88.50 Repair Melds 81.51 Settilne Region

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d TOTAL OF 26 ITEMS 4

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10 YEAR INSERVICE INSPECTION Vi 1OUISI AMA P(Ruf R A8R) LIGHT teATERTORO STE Am Et ECTRIC ST ATION UNIT NO. 3 i

INSERVICE INSPECTION PROGRAW FOR C1 ASS 1, 2. AND 3 C(M40KMTS EXAulteAIION CAltGORY 5-8 IUIAL EXAMINATI(BI IT[a IG.

AAEAS ERASIIED PER ITf m M ilRR)

RELIEF /rrumerNTS PressurSzer 82.10 Shell-to-Head Welds 82.11 Circumferential 2

Volumetric Fig 18 82.12 Longitudinal 4

Volumetric Fig 2B B2.20 Head Welds B2.21 C1rcumferent1al 82.22 IIeridional Steam Generators (Primary Side) 82.30 Head Welds 82.31 Circumferential 10 volumetric Fig 38 82.32 IIeridional IB Volumetric Fig 38 82.40 Tubesheet-to-Head Weld 2

Volumetric Fig 68 Heat Exchangers (Prteary Side) - Head 82.50 Head Welds 82.51 Circumferenttal 82.52 merldlonal i

B2.53 Longitudinal Shell (Primary Side) j B2.60 Tubesheet-fo-Shell (or Head) Welds B2.61 Tubesheet-to-Shell Welds TOTAL OF 36 ITEstS sneesonoises a

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13 YEAR INSERVICE INSPECTION V1 LOUISIANA POWER AND LIGfT WATERFORO STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAW FOR CLASS 1, 2, AND 3 COIR 0NENTS EXAMINATION CATIGORY H-D IUIAL EXAMINAT I(M ITEM 8E).

AREAS EXAMIM D PER ITEM K it(ID RELIEF /rriamKNTS Reactor Vessel 83.90 Nozzle-to-Vessel Welds 6

Volumetric Fig 78 B3.100 Nozzle Inside Radius Section 6

Volumetric Fig 78 PressurSzer 83.110 Nozzle-to-Vesse Welds 5

Volumetric Fig 78 83.120 Nozzle Inside Radius Section 5

Volumetric Fig 78 Steam Generators (Primary Side) 83.130 Nozzle-to-Vessel Welos 6

Volumetric Fig 78 83.140 Nozzle Inside Radius Section 6

Volumetric Fig 78 Heat Exchangers (Primary Side) 83.150 Nozzle-to-Vessel Welds 83.160 Nozzle Inside Radius Sectton TOTAL OF 34 ITEMS a

54 FSP 49/101485-3 16 i

l 13 YEAR INSERVICE INSPECTION REV l LOUISI ANA POWER AND LIGli WATERFORD STEAM [LECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAN IOR CLASS 1, 2, AND 3 COaFONENTS EXAulNATIDN CAlfC418tY B-E IUIAL EXAMINAT I(M ITEM 90.

AREAS EXANIE D PER ITEM Mit0D RELIEF /C M NTS B4.10 Parttal Penetrat100 Welds 84.11 Vessel Nozzles B4.12 Control Rod Drive Nozzles 91 Visual, VT-2 84.13 Instrumentation Nozzles 10 Visual, VT-2 i

Pressurtzer B4.20 Heater Penetratton Welds 30 Visual, VT-2 1

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i TOTAL OF 131 I TERIS 4

5478P 49h01485-4 17 4

13 YEAR INSERVICE INSPECTION P REV 1 LOUISIANA P(MER ADE) LIQlf WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1. 2, AND 3 COMPONENIS IXAMINATION CAlfGORY 8-F TOTAL EAAMINATIUM ITEM DE).

AREAS EAANIED PER ITEM KIHilD RELIEF /CO N NIS Reactor Vessel B5.10 Nominal Pipe Size > 4 in.

Nozzle-to-Safe Endl utt Welds 85.20 Nominal Pipe Size < 4 in.

Nozzle-to-Safe End Butt Welds 85.30 Nozzle-to-Safe End Socket Welds Pressur1zer 85.40 Nominal Pipe $1re > 4 in.

Nozzle-to-Safe Endlutt Welds 5

Volumetric & Surface Fig 88 B5.50 Nominal Pipe Stre < 4 in.

Nozzle-to-Safe End Butt Welds B5.60 Nozzle-to-Safe End Socket Welds Steam Generator 85.70 Nominal Pipe Stre > 4 in.

Nozzle-to-Safe Endlutt Welds B5.80 Nominal Pipe Size < 4 in.

Nozzle-to-Safe End Butt Welds B5.90 Nozzle-to-Safe End Socket Welds Heat Exchangers B5.100 Nominal Pipe Size > 4 in.

Nozzle-to-Safe Endlutt Welds B5.110 Nominal Pipe Size < 4 in.

Nozzle-to-Safe End Butt Welds B5.120 Nozzle-to-Safe End Socket Welds CONIINUED 18

l 13 YEAR INSERVICE INSPECTION P REV 1 LOUISI ANA POWER AND LIGli WAirRFORD STEAM ELECTRIC STATION (MIT NO. 3 INS [RVICE IMa.'ECTI(M PROGRAM F OR Cl ASS I 2 AND 3 CORIPONENIS EXAEINATION cal [ GORY 8-F (continued)

TOTAL EXAMINATI(M ITEM 8G.

AREAS EXAMI9ED PER ITEN E TMID REl_IEF/C M NTS Piping B5.130 Nominal Pipe Size > 4 in.

Disstellar metal Butt Welds 15 Volumetric & Surface Fig 8B B5.140 Nominal Pipe Size < 4 in.

Disstellar Metal Butt Welds 9

Surface Fig 88 B5.150 Dissimilar Metal Socket Welds 1

TOTAL OF 29 ITERIS T

$4FSP49/801485 6 19

10 YEAR INSERVICE INSPECTION V1 LOUISIANA PONER AND LIGtT WATERFORD STEAN ELECTRIC STATION UNIT ND. 3 INSERVICE INSPECTION Pet 0 GRAM fOR CtASS 1, 2 AND 3 COIFONENTS FAAMINATION CAIEGORY R-G-1 IUIAL ERABINATI(Ni ITEM 90.

ARIAS EXANIE D PER ITEM Kit 0D RELIEF / N NTS Reactor Vessel B6.10 Closure Head Nuts 54 Surface 86.20 Closure Studs, in place B6.30 Closure Studs, when removed 54 Volumetric & Surface Fig 11B B6.40 Threads in Flange 54 Volumetric Fig 118 B6.50 Closure Washers, Bushings 54 Visual, VT-1 Pressurtzer 86.60 Bolts & Studs B6.70 Flange Surface, when connection disassembled 86.80 Nuts. Bushings, and Washers l

Steam Generators 86.90 Bolts and Studs 86.100 Flange Surface, when connectton disassembled B6.110 Nuts, Bushings, and Washers Heat Enchangers 86.120 Bolts and Studs l

B6.130 Flange Surface, when connectton j

disassembled B6.140 Nuts, Bushings, and Washers 1

CONTIDRAED wereenesses F l

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l 10 YEAR INSERVICE INSPECTION NEV 1 LOUISI ANA P(BER A0R) LIG(T teATERFORO STEAM (LECTRIC STATION UNIT ND. 3 INSERVICE INSPECTION PROGRAW EUR Cl AS$ 1

2. AND 3 CORPONENTS EXAMINATION CATEGORY 8-G-1 (contsnued)

IUTAL

[AmmisenTIUse I T E 5 3R).

ARI AS ERABIBED PER ITEM K TM]D RELIEF /rflumrNTS Piping B6.150 Bolts and Studs 96.160 F1ange Surface, when connection dIsassembIed B6.170 Nuts Bushings, and Nashers Pumps 86.180 Bolts and Studs 4 Pumps Volumetric Fig 115 (64) 86.190 Flange Sur' ace, when connectton 4 Flanges Fig 118

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1 disassemoted (64)

Visual, VT-1 i

B6.200 Nuts, Bushings, and Washers 4 Pumps Visual. VT-1 (64) i i

Valves l

86.210 Bolts and Studs 96.220 Flange Surface, when connectton t

i disassemoved B6.230 Nuts, Bushings, and Washers i

TOTAL OF 400 ITEMS

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sereresneieos e 21 1

10 YEAn INSERVICE 18tSPECTION REW 3 1.0UI5I48e4 PGutR AND t_IQfT wtTEnf 0RO STI AEI Et ECTRIC ST ATION UNIT NO. 3 INSERVICE tetSPECTION P90GRAW F OR CLASS 1, 2, Ase) 3 C(MOENTS EXAmtleATION CAlfGORY 8-C-2 rpIAL

[KAulpeATI(NE ITES 30.

AMAS EXASItED PER ITEM K il(M)

RELIEF /fYImmFNTS Reactor vessel 87.30 Bolts. Studs, and Nuts PressurSzer 87.20 Solts, Studs, and Nuts 1

Visual, VT-1 Isanway l

Steam Generators l

l 87.30 Solts, Studs, and Nuts 4

Visual, VT-1 j

Manways l

Heat Exchangers 87.40 Solts. Studs, and Nuts Piping i

87.50 Bolts. Studs, are nuts 2

Visual, VT-1 FIanges Pumps 87.60 Solts. Studs, and Nuts 4 Sets Visual, VT-1 of Seal BottIng Valves 87.70 Solts. Studs, and Nuts 20 Visual, VT-3 t

l Valves CRD Housings 87.80 Bolts, Studs, and Nuts TOTAL OF 31 ITEMS sereceeneseos e 22 l

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10 VEAR INSERVICE INSPECTION HEV 1 i

LOUISI AMA P(BIER A8G LIG4i WATERFORD STEAN ELECTRIC STATION UtilT DC. 3 INSE RVICE INSPECTION PROGRAM IOR C1 ASS 1, 2. A8e 3 CGIr00ENTS 4

EXAmite4 TION CAIEGORY 8-H IUIAL ENANTHATIEBE ITE5 30.

ARE AS EXAEltED PER I TEM K IFEID RELIEF /rrimmsFNTS Reactor Vessel B8.10 Integrally Welded At tacrunents Pressurizer 88.20 Integrally Welded Attachments 1

VolumetrtC or Surface fig 128 Steam Generator 88.30 Integrally Welded Attachments 2

volumetric or Surface Fig 128 Heat Exchangers i

88.40 Integrally Welded Attachments l

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TOTAL OF 3 ITEMS J

snee eenei.es-se 23

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l 10 YEAR INSERVICE INSPECTION P REV 1 LOUISI ANA PONER AND LIGIT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INS [RVICE INSPECTION PROGRAM FOR CLASS 1, 2, AND 3 COMPONENTS EXAMINATION CAlfGORY B-J TOTAL EXAMINATION ITEM M).

AREAS EXAMIW.D PER ITEM ETH00 RELIEr/COMENT S B9.10 Nominal Pipe Size 1 4 in.

B9.11 Circumferential Welds 318 Volumetric & Surface Relief Request ISI-OOl/ Fig 88 89.12 Longitudinal Welds 64 Volumetric & Surface Relief Request ISI-OO1/ Fig 88 B9.20 Nominal Pipe Stre < 4 in.

89.21 Circumferential Welds 361 Surface Fig 88 09.22 Longitudinal Welds 89.30 Branch Pipe Connectton Welds 89.31 Nominal Pipe size 1 4 in.

7 Volumetric & Surface Rellef Request ISI-OO1/ Fig 108 B9.32 Nominal Pipe Size < 4 in.

13 Surface Fig 98/ Fig 100 89.40 Socket Welds I

i TOTAL OF 763 items l

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13 YEAR INSERVICE INSPECTION P REV 1 LOUISI ANA P(RIER ADE) LIGtT WATERFORD STEAaB ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 COIFONENTS i

EXAMINAT ION CAT [GIItY B-K-1 TOTAL EXABINATI(BI ITEM 00, ARE AS [XAMIIED PER ITIM K itW10 RELIEF /C M NTS 1

Piping B10.10 Integrally Welded At tactwnents Pumps 810.20 Integrally Welded Attachments 4

volumetric or Surface Fig 128 Valves 810.30 Integrally Welded Attachments l

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TOTAL OF 4 ITERES 1

1

$4?SP49/10t405 t2 5

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13 YEAR INSERVICE INSPECTION P REV I LOUISIANA PGUER AND LIGli WATERFORO STEAM ELECTRIC STATION UNIT ND. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 CDer0MENTS EXAMINATION CATEGORY R-L-1 D-L-2, R-5-1 A85) 5-5-2 IUIAL EXABINATI(BI ITEM M).

AREAS EXABIE D PER ITEM KTM]O RELIEF /C M NTS Pumps 832.10 Pump Casing Welds (B-L-1) 8 Volumetric Relief Request ISI-OO4 812.20 Pump Casing (B-L-2) 4 Visual, VT-3 Rettef Request 1S1-004 i

Valves 612.30 Valves. Nominal Ptpe Size < 4 in.

Valve Body Welds j

B12.40 Valves, Nominal Pipe Size > 4 in.

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Valve Body Welds (B-M-1) 2 Volumetric Fig 13B B12.50 Valve Body. Exceeding 4 in.

1 Nominal Pipe Size (B-M-2) 22 Visual, VT-3 Rellef Request 151-003 i

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TOTAL OF 36 ITERIS 547sP 49/10t ee5 13 26

13 YEAR INSERVICE INSPECTION P REV I LOUISIANA POWER AND LIG1T WATFRFor!D STEAM tLECTRIC STATION tMIT NO. 3 IiGERVICT INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 CORFONENTS EXAMINATION CATEGORY R-N-1 B-N-2 Ale B-N-3 TDTAL EXAMINATI(M ITEM NO.

AREAS EXAMIED PER ITEM KTHOD RELIEF /rrimmrNTS Reactor Vessel B13.10 Vessel Interior (B-N-1) 1 Vessel Visual. VT-3 Reactor Vessel (PWR) 813.30 Interior Attachments Within Beltline Region (B-N-2) 6 Visual, VT-1 B13.31 Interfor Atiachments Beyond Belti1pe Region (B-N-2) 9 Visual. VT-3 B13.32 Core Support Structure (B-N-3)

I Vessel Visual, VT-3 TOTAL OF 17 ITEstS s478P 49/101485-14 27

1D YEA 3 INSERVICE INSPECTION P REV 1 LOUISI ANA PGWER AND LIGil WATERFORD STEAM ELECTRIC STATION IMIT ND. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 COMPONENTS EXAMINATION CAitGORY B-0 TOTAL EXAMINATI(M ITEE le.

ARLAS EXAMIE D PER ITEM Kil0D RELIEF /CQ K NTS Reactor Vessel 814.10 Welds in CRD Housing (Upper) 32 Volumetric or Surface Fig 148 Welds in CRD Housing (Lower) 32 volumetric or Surface F1g 148 i

r i

1 4

k TOTAL OF 64 ITERS t

d

$4 FSP 49/801445-IS i

l 28 i

13 YEAR INSERVICE INSPECTION P V1 LOUISIANA PONER AND LIQli WATEREORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM TOR CLASS 1, 2. AND 3 COMPONENTS EXAMINATION CAIEGORY B-P TUTAL EXANTNATION ITEM NO.

AREAS EXAMIK D PER ITEM K itE10 RELIEF /C M NTS Reactor Vessel B15.10 Pressure Retalning Boundary Note 1 Visual, VT-2 B15.11 Pressure Retalning Boundary Note 2 Visual, VT-2 Pressur1zer D15.20 Pressure Retalning Boundary Note i Visual, VT-2 015.21 Pressure Retalning Boundary Note 2 Visual, VT-2 Steam Generators B15.30 Pressure Retalning Boundary Note 1 Visual, VT-2 B15.31 Pressure Retalning Boundary Note 2 Visual, VT-2 Heat Exchangers B15.40 Pressure Retalning Boundary 815.41 Pressure Retalning Boundary Piping 815.50 Pressure Retalning Boundary Note 1 Visual, VT-2 I

B15.51 Pressure Retaining Boundary Note 2 Visual, VT-2 Pumps B15.60 Pressure Retalning Boundary Note 1 Visual, VT-2 015.61 Pressure Retalning Boundary Note 2 Visual, VT-2 Valves B15.70 Pressure Retaining Boundary Note 1 Visual, VT-2 B15.71 Pressure Retaining Boundary Note 2 Visual, VT-2 NOTES:

su The p esse <e,ete+.eas bocaderv de<*as the systea= 8eaksee test shan car'**pead to the,*.cto, caos at syste bos.d.,, with en e.%s s the e,m.:

posstoon wh6ch is #94eeeed foe asemal seeClor opetelo n startup The VT-2 enamesation shan, however estead to end 6 clude the second closed wa%

o et the boundary estese6fy (2)

The pressere rete 4 ming boundary dettog the system hydrostat4C test th4N entlede en Qass I components weth the system boundary 5478P 49/t el405-16 29

10 YEAR INSERVICE INSPECTION P REV 1 LOUISIANA POWLR AND LIGli WATERFORD STEAN ELICTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PHOGNAM f()R CLASS 1, 2. AND 3 CORPONENTS

[AAMINATION CATIGORY H-Q 1

TOTAL EKAMINAT I(N4 ITEM NO.

AREAS EXAMIE D PER ITEM KTHDD RELIEF /C M NTS B16.10 Steam Generator Tubing in Straight Tube Design 816.20 Steam Generator Tubing in U-Tube Design 18.700 Volumetric Per LP&L Tech Specs 4.4.4 i

I l

1 i

I TOTAL OF 18,700 ITEllIS i

serse aseiosees-si I

30 d

(

rh t

(

i

\\

v' rn I

l m

n n

it - y N

N

== m i k g l am p g g g

g g m>

g o

R E

50 m CO I E

5' 5'

se m o

$<g 8

O i

r 2OI m

4 i

Mn o

i U

m p

p

/,

r-p 4

5;

~

m Y

2 o

g j

I C

z E

I X

l u)

~

g

/

X, Ti i

m A

l p-(

m

}

8 i(I 2

1 i

I m

o g

v N

l N

-A i

2 l

3m w

-i "n

N '*

4 W

t c> -

1. 3*

-l/a '2 CZ Dr m/a'2-

._ gje t g -

D u)

A T

(

I l

I

_m l

m 8

mO i

r "M W.

I Enem. vol.

-1 0

E-F.g,H

,_g_g_g g

l 2

.I c._

O, y

2 m

-1 Scon area os required to enomene I

o

~

U)

_Scon area os requried to enormne+

vol. A-B - C-D O

vol. E - F-G- H I

l 8

i K

L t

j Y

y WVessel Shell-Hood Joint (o) Vessel Shell Courses 4

4 h

m f_

10 YEAR INSERVICE INSPECTION PROGRAM REV.6 FIGURE 2B O

A l

~

N

[

jo 39 sp f?

w iM8,92,,v.-- d> hf lO

(

Longtudinol 4

-?

O wg 34 o

f 33 3

%w

'g g.{

D C

Q Clodding N

l O

VESSEL SHELL LONGITUDINAL WELD JOINTS I) REACTOR VESSEL

2) PRESSURtZER 32 i

10 YEAR INSERVICE INSPECTION PROGRAM REV.I FIGURE 3B s

C X

A N

8 x-s,&

r N.o

.?

4l4l

. o 0

d A

C E4 h

R

- fj'

/

A A

B j'

~. -

E

'5 T'.

s 4

?

3?

'S M

W >XQXf

"*d'"*'

1 gz

-~

m

.e 4

5 I+

1 d(

g B}

k H

gg l-dl I

I G

~

Circumferential weld 1

\\

Section B 8 8

~%

View A A SPHERICAL VESSEL HEAD CIRCUMFERENTIAL & MERIDIONAL WELD JOINTS

1) REACTOR VESSEL 80TTOM HEAD

2) REACTOR Ct.OSURE HEAD

3) STEAM GENERATOR PRIMARY HEAD 33..

i 10 YEAR INSERVICE INSPECTION PROGRAM s e v.,

FIGURE 48 1

4 i

i l

l l

l i

i i

i i

l i

g i

8 1

8 1

s i

e i

I I

i

^

9 a

E 19 i

rya g y 7 4 Q, Circumferential lY 1

• • 'd l

_f w*

5

-~'

i r

t

=

- Cloddhg

--a i

=

t 4

i O

REACTOR VESSEL SHELL-TO-FLANGE WELD JOINT 34

I 10 YEAR INSERVICE INSPECTION PROGRAM nevi FIGURE 58 O

4 s

1 s

.O

% N

%.D

%e b\\k S

h

/

~~ /

e

% [

4

• c g,

[

O

/

c/

l I

t ij N

3m

]

t#

i l

Clodeng -

t t a

REACTOR VESSEL CLOSURE HEAD-TO-FLANGE WELD JOINT i

35

aee Ee-_.im.j

_w_

a.m, m

.m

.-:,m_

_a 10 YEAR INSERVICE INSPECTION PROGRAM nev.s FIGURE 68 O

l i

N t

l 1,

j a

f'

}

A h

j s

3 d

2

• e, s.

\\

c u

o y V

\\

-s 0

N, g

I) d a

y h

g.

01 l

==

i >

t 8

m j

5 pV c

M i

C f

d STEAM GENERATOR TU8ESHEET-TO-HEAD WELD JOINTS i

l 36 i

I J

10 YEAR INSERVICE INSPECTION PROGRAM sEvi FIGURE 78

^N e

I\\

l tl l

NOTES:

t l

', gl fnt, in2 s nostle wall thicknese l

to isnei:(or beod) thicknese sl i

1 in g --.

f

,4

'h k

O 'sN p*{,C y

0

- N:

g I

lN I

f l

Y l

!{!{!'

l e,

g it i i i

9 i

1 wI

\\

l

}

=

F E

M'l Clodding where i

present in2 --*

I Emorn. vot A-B C 0 E-F G H l EXAMINATION REGION EXAM 6 NATION VOLUME Shell (or hood) odpeng regen C0EF Attachtnent weld region BCFG Norsie cylinder region A8GHl Nozzle inalde corner region MNOP NOZZLE-TO-VESSEL WELDS (Examination Zones in Borrel Type Nozzles Joined by Full Penetration Corner Welds)

O o Re c'eR coo' ~r ~orr'

-'o-R scroR ve

2) REACTOR COOLANT, NOZZLES-TO STEAM GENERATOR l

3) PRESSURIZER SURGE NOZZLE-TO PRESSURIZER l

4)PRESSURt2ER SPRAY NOZZLE TO PRESSURIZER

5) PRESSURIZER SAFETY NOZZLES-TO PRESSURIZER I

37

10 YEAR INSERVICE INSPECTION PROGRAM R E v.

FIGURE 88 Profile of volve body, vessel

_ Enom. surface

[ norte,or pump connection

,-g

)'

-~

sta an.

att in Wold end bu,tering(where coplied)

{l h >

h '

a*

\\

k$ h

\\

' F'

'E\\

k g

- t/ec +

-. iAin Enom. vot C-D- E F (c)NPS 2 4in.

Enom. surfoce

~

Profile of volve body, A.g veteel nogale, or pump connection p

1/ tin */*

Itt in y <,

-,. en. bu,,e,,, (. ore opp,,ed, f

b nner sufoce i

\\

(b) NP s < 4ln.

O SIMILAR & DISSIMILAR METAL WELDS IN COMPONENTS S PIPING 38

10 YEAR INSERVICE INSPECTION PROGRAM sev. i FIGURE 98 s

V 7w h

D h

a f

- N l

r[

^

/

CV r'/ x

\\

._\\

S S /

x *l Ei i

I

/

Brech

/

I connection o

~

~~\\,

e

$~1

\\f

)

i 5

k' N I

weld joint-=

l

-sv

]

J W: _

MJ k

f*

O PIPE BRANCH CONNECTION I) 3" HPSI connections to 14" Shuteen Cooling

2) 3" relief volve connections to 14" Shutdown Cooling 39

10 YEAR INSERVICE INSPECTION PROGRAM REVI f

FIGURE 10B

/k g

e D.

N

,,,, A,

,k E

^

{

~

~

l e-lh +

BF0fiCh Connect:0n f

-*" lift "*-

-j g

Fo e E

E Dy 8

\\

t o

J

.4 N, 4

~

NOTE Emomination volumes C-D E F ore def,ned per Fig.88 PIPE BRANCH CONNECTION C

1) PRESSURIZER SURGE CONNECTIONS TO REACTOR COOLANT PIPING

2) SAFETY INJECTION CONNECTIONS TO REACTOR COOLANT PIPING

3) SHUTDOWN COOLING CONNECTIONS TO REACTOR COOLANT PIPING

4) CHARGING S LETDOWN CONNECTIONS TO REACTOR COOLANT PIPING

5) PRESSURIZER SPRAY CONNECTIONS TO REACTOR COOLANT PIPING

6) DRAIN CONNECTIONS TO REACTOR COOLANT PIPING 40

10 YEAR INSERVICE INSPECTION PROGRAM mi FIGURE IIB i

/

O 1

l

\\

N'-

Center drill hole J_

Fj l *I l '1 1

I I

l l l

1 l

l 1

I l

l 1

l i

I l

l e

r I

i l

i p

STUD I

I I

I l

l ll vieval enom. creas B C for reactor coolont pumps Enon vol.

i I

I I

1 i

1 l

F

! oce of flonge

-+

Iirt I

C'...B I lW l

o I

I l

l l

l i

j Og, l

l Il g

j i

I

• Enom. vol, throods in l

8 flange (A B C 0)

I l

OI A

for reactor veteel l l Illi

~*M L

g 7

9. Stud NOTE:03 s the diometer of the stud.

i STUD EXAMINATION O

1) Reactor coolont pump stude

2) Reoctor closure stude

3) Flonge surfoce/ Threads in flonge 41

10 YEAR INSERV!CE INSPECTION PROGRAM pcvi FIGURE 128 O

I t

/

/

/

Y

//

f /

/

/

/

l ll l //

l

/

}

Vn

'k h

D

,C V8 In it

+=lntegral ottoenment i

f IW S Soundary Surf. esem orcos A B ond C 0 I

t lO SUPPORT SKIRT WELDS l

0 sf.om o neratere i

2) Precove6 er l

3) AC Pumpe 42

10 YEAR INSERVICE INSPECTION PROGRAM REVi FIGURE 138 O

V l

T. Volve I

I f

t

]

7 O

I I

I S

i I

i i

E1

.f

)M'/

/,,a n-.

--v. m.

I t

O f agm. wel.

t EF0H j

PRESSURIZER SAFETY WLVE BODY WELDS 43

10 YEAR INSERVICE INSPECTION PROGRAM sev.i FIGURE I4B O

i l

}

t/t in *=

-* t/t in.

A,.

,9

/

hh"__

l I

D'

(.,,g "C

buttering

]i UPPER WELD O

~

t/t in.

~

I/2 in.

+-

A, i

^ :-

IIL g

l l

0" (se6d butter 6ag C

LOWER WELD i

Enomination Volume A B C 0 Surfoce Enemination Area A 8 l

l CONTROL ROD DRIVE HOUSING WELDS 44

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 OV 3.0 INSERVICE INSPECTION OF CLASS 2 COMPONENTS Based on Table IWC-2500-1, the examination categories and items identified in the Examination Table are subject to examination under LP&L's Inservice Inspection Program. The Examination Table identifies the non-exempt components subject to examination, the total number of items under each category, Relief Requests associated with each item, and figure number if applicable. The Examination Table is followed by figures which illustrate and define the inspection boundaries of each item. All welds whose stress levels exceed that shown in IWC-2500-1 (Cat C-F) are examined. Additional details regarding exemptions and system pressure tests are addressed below.

3.1 Exemptions (IWC)

O The following exemptions apply to all applicable categories of IWC-2500-1. Also, the selection of supports under IWF is affected.

3.1.1 IWC-1220(A)

As allowed by this paragraph, all Class 2 systems or portions of systems that during normal plant operation are not required to operate or perform a system function but remain flooded under static conditions at a pressure of at least 80% of the pressure that the component or system will be subjected to when required to operate are exempt from this program. This exemption applies to the four (4) Safety Injection Tanks which during normal operation remain flooded under static conditions at 100% of the pressure that the tanks will be subjected to when required to operate.

3.1.2 IWC-1220(B)

As allowed by this paragraph, all Class 2 components of systems or portions of systems, other than Residual Heat Removal Systems and Emergency Core Cooling Systems, that are not required to operate above a pressure of

\\

275 psig or above a temperature of 200*F (93*C) are exempt.

This exemption applies to the following Class 2 lines:

W340076E 45

10 YEAR INSERVICE INSPECTION PROGRAM l

Rev. 1

's 2CS10-12A 2CC8-88A1 2CS10-12B 2CC8-88A2 j

2CS6-13A 2CC8-91B1 2CS6-13B 2CC8-91B2 2CS8-14A 2CC10-151A/B 2CS8-14B 2CC10-153A/B l

2CS6-15A 2CC8-157Al 2CS6-15B 2CC8-157A2 2CS6-16A 2CC8-158B1 4

2CS6-16B 2CC8-158B2 2CS6-18A 2FS6-64A/B

+

i 2CS6-18B 2SA10-103 I

3.1.3 IWC-1220(C)

As allowed by this paragraph, all Class 2 component connections (including nozzles in vessels and j

pumps), piping and associated valves, and vessels and their

)

attachments that are 4 inch nominal pipe size and smaller e

are exempt from this program. This exemption applies to all j

piping < 4" nominal pipe size.

3.2 System Pressure Tests (IWC)

As required by Tables IWA-5210-1 and IWC-2500-1 the system pressure tests described in IWA-5211 are conducted as follows:

l t

i i

W340076E 46 4

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1

s(J 0.2.1 Hydrostatic Testing (IWA-5211d)

The hydrostatic testing requirements of IWC-2500 are required to be performed at or near the end of each Inspection Inter-val. The procedures detailing the hydrostatic testing and any Relief Requests associated with these tests will be developed during the second period of the first Interval. All hydro-static testing required due to repair / replacement activity is handled on a case by case basis. The hydrostatic tests and associated repair / replacement activities are documented on NIS-II forms which are submitted with an Outage Summary Report to be filed after refueling outages.

3.2.2 System Functional Test (IWA-5211b)

During each Inspection Period, the Class 2 pressure boundary

(

of those systems or portions of systems not required to operate during normal reactor operation is subjected to a visual exam (VT-2) while at the pressure obtained during the system or component functional tests. The pressure retaining boundary extends up to and including the first normally closed valve or valve capable of automatic closure when the safety function is required.

3.3 Examination Table and Figures 1

W340076E 47

10 YEAR INSERVICE INSPECTION V1 LOUISIANA PONER AND LIQli teATERFORO STEAM ELECTRIC STATION UNIT ND. 3 INSERVICE INSPECTION PROGRAgI FOR CLASS 1, 2, AND 3 Cor 0NLMIS ERAmladATION CATEGORY C-A ruv AL.

EXAWIIERTIINE ITER DE).

AIKAS ERAEIDED PER ITER M TMID REL IEF/rsimensFNT S i

Cl.lO Shell Circumferenttal teelds to volumetric fig IC i

C1.20 Head Ctrcumferenttal Welds 4

Volumetric Fig IC C1.30 Tubesheet-to-Shell weld 4

Volumetric Fig 2C l

r

'i i

e l

l TOTAL OF 18 ITEEE5 i.

4 i

48 i

10 YEAR INSERVICE INSPECTION W1 l

l l

EOUISI Asen P(BER Ace LIGti WATERFORD STEAM ELECTRIC STATION UBIIT M. 3 IseSERVICE IIESPECIION Penrman y0R CLASS 1, 2. Ace 3 CupOBENIS ERAmsteATI(Be Cait GIstY C-5 IUIAL EXAWilenT auss ITES W.

AKAS ERASIMD PER ITES M IMMD RE L IE F/CEM NTS C2.lO 9eozzles in vessels <-1/2 in.

j

~

j Nominal Thtchness C7 Il Nozzle-to-Shell (or Head) Weld l

C2.20 seozzles without Retnrarcing Plate in Vessels > 1/2 in. peontpal Thtchness C2.21 Deozzle-t o-Shel l (or Head) Weld 4

Volumetric & Surface Fig 3C C2.22 peozzle Instde Radius Sectlers a

Volumetric Fig 3C C2.30 seozzles with Retnforcing Plate in Vessels > t/2 in. teominal Thickness C2.31 Retnforctng Plate Seelds to Benzzle and vessel 8

surface Fig 3C C2.32 Nozzle-to-Shell (or Head) Seelds Instde of Vessel Accessible Inside of vessel Inaccessible 4

Visual, VT-2 TOTAt. IF 20 ITEMS saar e w w no AG

I

\\

10 VEAR IeISEevlE ItI5PECTICIe AEW I LGBI$lafen PEMR Age LIGfi teniEEIFGm3 SIEas ELECinIC STATIGIISpeli se. 3 Beu5Emwfu Iss5PECIIGus renomaan yon QA55 8, 2. Ace 3 CNestS EAmassent adme CattEmery C-C ruvat smausy s IIEW W.

ANASERM MS PER ITES W IDE3 Nt_IEF/f1RumuFagf5 Pressure Wessels t

C3.10 Integrally useided Attachments 8

Surface Fig 4C Ptptng C3.: 0 Integrally teelded Attachments 24 surface Fig 4C C3.30 Integrat1y use1oed Attachsents 6

Surface F tg 4C Valwes C3.40 Integratty welded attachments l

t l

TOlat W 33 items Se79Peptes e 33 l

l l

50

____.m.

l to vtAR 196ERVIE ISESPECTION V1 I

tou!SIAsen PmER Ase LIGfi tenIEnFERID STEae ELECTRIC STATION useIT 8E3. 3 II6ERVICE 186PECTICBs N FOR CLASS 1, 2. Ace 3 CMests j

EXAmetenTIoss CAircoRY C-D

)

4 iUiAL E m uutTIENU Tif s IS.

ANAS EXASBIED PER ITES K it e MLIEF/CMI8tS Pressure Wessels i

C4.lO solts and Studs Piping C4.20 Bolts and Stuos

)

Pueps I

C4.30 Bolts and Stuos Valves

)

C4.40 Bolts and 5 tuns 1

1 4

l i

i i

TOTAL (F 0 ITEMS i

seiereonesass as 51 d

13 YEAR INSERVICE INSPECTION P REV 1 LOUISI ANA P()WER AND LIQlT WATERFORD STEAM [LECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAW FOR CLASS 1. 2. AND 3 CORPONENTS EXAMINATION CATEG)RY C-F TOTAL EXAMINATION ITEM DE).

AREAS EXAMINED PER ITEN GETHDD RELIEF /CO M NTS C5.10 Piping Welds i 1/2 In.

Nominal Wall Thickness C5.11 Circumferential Weld 503 Surface Relief Request 151-001 ISI-OO2/ Fig SC C5.12 Longitudinal Weld 81 Surface Fig SC C5.20 Piping Welds > 1/2 in.

Nominal Wall Thickness C5.21 Circumferential Weld 229 Volumetric & Surface Rellef Request ISI-OO1/ Fig SC C5.22 Longitudinal Weld 30 Volumetric & Surface Relief Request ISI-OO1/ Fig SC C5.30 Ptpe Branch Connections > 4 in.

Nominal Branch Pfpe Size C5.31 Circumferential Weld 3

Surface Fig 6C/ Fig 7C C5.32 Longitudinal Weld TOTAL OF 846 ITEGIS i

smeonoies 2 52 i

13 YEAR INSERVICE INSPECTION P VI LOUISI ANA PUNER AND LIGIT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2 AND 3 COOFONENTS EXAMINATION cal [ GORY C-G i

TOTAL EXAMINATION ITEM 90.

AREAS EXAMIE D PER ITEM K itt)O RELIEF /C M NTS Pumps C6.10 Pump Casing Nelds Valves C6.20 Valve Body Nelds 4

Surface Fig 8C 1

j I

i i

TOTAL OF 4 ITEMS

}

5478P 49/801485 23 i

53

l 13 YEAR INSERVICE INSPECTICM V1 LOUISIANA POWER AND LIGif WATERFORD STEAM [LECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR Ct_ ASS 1, 2 AND 3 COWONENTS EXAMINATION CAIEGORY C-il TUTAL EXAMINATION ITEM 95).

AREAS EXAMIE D PER ITEM E T1100 RELIEF /C N NIS Pressure Vessels C7.10 Pressure Retalning Components Note 1 Visual, VT-2 C7.20 Pressure Retalning Components Note !

Visual, VT-2 Piping C7.30 Pressure Retalning Components Note 1 Visual, VT-2 C7.40 Pressure Retalning Components Note 1 Visual, VT-2 1

Pumps C7.50 Pressure Retalning Components Note 1 Visual, VT-2 C7.60 Pressure Retalning Components Note 1 Visual, VT-2 Valves C7.70 Pressure Retalning Components Note 1 Visual, VT-2 C7.80 Pressure Retalning Components Note 1 Visual, VT-2 NOTES:

(1)

The pressure rete *a6ag bewadeey sacludes saly these posteens et the system sequeeed to opeeste er support the safety system tumCito# Up to and 4ACledepg Itbo sugt neemaHy closed valve (6ncludeng a safety es rehet valve) er valve tapelde et estomalet caeswee when the safety tuaceton 6e reggered f

s4ree.enoises. '

54 i

10 YEAR INSERVICE INSPECTION PROGRAM REv.i FIGURE IC OV i

1/2 in.

D.

..A 6

.h.ti to h.od M

i Enom. vol A-B-C-D q

circume.r.ntici io C'

~

"B 4

t/z in.

(c) n.

HN'N Cylindr,ical to conical _h o

cir_.,.n,m,..,.

G e $

Enorn. W

~

F E r.g, (b) t/2 in.

M..

J t I

Conical-to-cylindricot M --

E vol J K-L M 4

circumferentici..w L

K f 1/2 in.

(cl O

SHUTDOWN COOLING HX & STEAM GENERATOR CIRCUMFERENTIAL WELDS 55 l

10 YEAR INSERVICE INSPECTION PROGRAM REV.I FIGURE 2C Exam vol A-B C D 1/2 in.

s A\\

t/2 irt D

~ _-

~

Tubesheet l()h G_

.H k'

f F"

'E 1/2 in.-*

~1/2 in.

E nom. vol. E-F- G-H --=

+--

l O

STEAM GENERATOR TUBESHEET-TO-SHELL CIRCUMFERENTIAL WELDS 56

10 YEAR INSERVICE INSPECTION PROGRAM REv.i FIGURE 3C O

x e

- A > Enom. surf. A-B

+ \\ @j t/a in.

s/a in.

(

..B (gej#'

k!"5"

?...

,~

r

,f. in.

h 8

C

_D t

+^#

(% '

di/

t 3,,p 1/4 in. -+-

Enom. vol.

C-D- E-F MAINSTEAM & FEEDWATER NOZZLES TO STEAM GENERATOR O

h Reinforcing picte h

A Telltale hole g

i/ain.

.--s/a in.

_B

_C 0%"h M.""=.

D V,"

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SHUTDOWN COOLING HX NOZZLE REINFORCING PLATE WELDS l

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10 YEAR INSERVICE INSPECTION PROGRAM R E V. I FIGURE 4C L

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INTEGRALLY WELDED ATTACHMENTS I) Steam Generators

2) Piping l

3) LPSI Pumps 58

10 YEAR INSERVICE INSPECTION PROGRAM REVi FIGURE SC O

Enom. surf.

Profile of volve body, vessel nozzle,or pump connection A-B

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59

10 YEAR INSERVICE INSPECTION PROGRAM nev.i FIGURE 6C O

• o9 c.,.

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8" SAFETY INJECTIOtt TO 14" SHUTDOWN COOLING PIPE BRANCH CONNECTION j

60

10 YEAR INSERVICE INSPECTION PROGRAM Rev.i FIGURE 7C O

Og 44%,

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8 w

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6" EMERGENCY FEEDWATER TO 20" MAIN FEEDWATER PIPE BRANCH CONNECTIONS 61

10 YEAR INSERVICE INSPECT 10N PROGRAM AEvi FIGURE 8C O

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i MAINSTEAM ISOLATION MLVE BODY WELDS O

I 62 l

10 YEAR INSERVICE INSPECTION PROGRAM l

Rev. 1 n

v 4.0 INSERVICE INSPECTION OF CLASS 3 COMPONENTS (IWD)

Based on ASME Section XI, Table IWD-2500-1, the examination categories and items identified in the following Examination Table are applicable to the Waterford 3 Inservice Inspection Program. Under the rules of IkT, examination of the entire support is required when the components are required to be examined by IWD. The IWD and IkT examination boundaries are specified in Fig. IhT-1300-1. Ultimately, the rules of the two Subsections require the same type of examination for the entire support.

Therefore, LP&L establishes the examination category for the integral attachment (IWD) portion of the support based on the IWF-2500-1 category applicable to the remainder of the support. The Class 3 supports are shown under Category F-A, F-B or F-C.

(See Relief Request No. ISI-005 and the Examination Table). With this approach, all of the required support examinations are performed as required by the ASME code, and the process of categorization and scheduling is greatly simplified.

O 4.1 Exemptions The following exemptions apply to all applicable categories of IWD-250d-1. Selection of supports under IWF is affected.

4.1.1 IWD-1220.1: As allowed by this paragraph, all Class 3 integral attachments of supports and restraints to components that are 4 inch nominal pipe size and smaller except for Emergency Feedwater (the Waterford 3 equivalent of Auxiliary Feedwater) are exempt from this program. Louisiana Power &

Light will apply this exemption to all Class 3 lines < 4" with the exception of the following Emergency Feed.iater lines:

O W340076E 63

10 YEAR INSERVICE INSPECTION PROGRAM l

Rev. 1 O

c EW SYSTEM ( $4")

Line No.

P 3W4-76A 3W4-77B 3W4-46 3W4-47 3W1\\-61 3CD4-67A 3CD4-68B 4.1.2 IWD-1220.2: As allowed by this paragraph, integral attachments of supports and restraints to components exceeding 4 inch nominal pipe size may be exempted from the visual examination (VT-3) of Table IWD-2500-1 provided:

I i

(A) The components are located 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.

i j

(B) The components operate at a pressure of 275 psig or less and at a temperature of 200*F (93*C) or less.

Louisiana Power & Light will apply this exemption to the following Class 3 lines:

LINE NO.

LINE NO.

3CC20-107A/B 3CC14-113A/B 3CC12-67A/B 3CC18-243A/B 3CC18-156A/B 3CC18-242A/B 3CC16-161A (From 3CC20-107A/B to 3CC-F120A) 3CC14-133A/B 3CC16-161B (From 3CC20-107A/B to 3CC-F121B) 3CC12-372A/B 3CC18-11A/B 3CC14-134A/B 3CC16-148A/B (From 3CC-F122A to 3CC-F123B 3CC10-154A/B to reducer at 3CC18-11A/B) 4 W340076E i

64

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1

()

LINE NO.

LINE NO.

3CC8-139A/B 3CD8-124 3CC8-119A/B 3FS10-2A 3CC6-142A/B 3FS10-3B 3CC10-68A/B 3FS12-1A/B 3CC10-152A/B 3FS10-5B 3CC10-13A/B 3FS10-4A 3CC10-21B1 3FS12-6A/B 3CC10-51B1 3FS12-7A/B 3CC10-66A/B 3FS12-51A/B 1

3CC10-15A1 3FS10-76A/B 3CC10-33B2 3FS10-77A/B 3CC10-78A/B 3FS6-66A/B 3CC10-57A2 3SI16-41A 3CC6-39A/B 3SI16-41B j

3CC6-317 3SI6-46A/B 1

3CC6-12A/B 3SI6-47A/B 3CC12-130A/B 3SI6-48A/B 3CC10-45A1 3SI6-180A 1

3CC10-63B2 3SI6-180B 3CC12-371A/B 3CC10-27A2 1

4.2 System Pressure Tests 1

i As required by Tables IWA-5210-1 and IWD-2500-1 the system pressure tests described in IWA-5211 are conducted as follows:

i

()

i W340076E l

65

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_~._. _

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 i

i i

t 4.2.1 Hydrostatic Testing (IWA-5211d) l I

The hydrostatic testing requirements of IWD-2500 are required i

to be performed at or near the end of each Inspection Inter-j val. The procedures detailing the hydrostatic testing and any Relief Requests associated with these tests will be developed during the second period of the first Interval. All hydro-j static testing due to repair or replacement activity is i

handled on a case by case basis.

4.2.2 Inservice Test (IWA-5211c) i During each Inspection Period, the Class 3 pressure boundary is subjected to a visual exam (VT-2) with the system (s) in service under operating pressure. The pressure retaining i

1 boundary extends up to and including the first normally i

closed valve or valve capable of automatic closure to perform the safety-related system function.

1 i

4.3 Examination Table k

i J

t

~

l W340076E d

, _ ~ _ _... _ - -.

66 4

13 YEAR INSERVICE INSPECTION P REV 1 t OUISIANA PONER AND LIGIT WATERfORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM 7 0R CLASS 1, 2, AND 3 CORFONENTS EXAMINATION CAff00RY D-A TDIAL

[KAMINATION ITEM NO.

AREAS EXAMINED PER ITEM KTHOD RELIEF /enans NTS DI.10 Pressure Retalning Components Note 1 Visual, VT-2 Pressure Retalning Components Note 1 Visual, VT-2 i

D1.20 Integral Attachment-Note 2 Visual, VT-3 Rellef Request 1S1-005 Component Supports and Restraints D1.30 Integral Attachment-Note 2 Visual, VT-3 Relief Request 1S1-005 Mechanical and Hydraulic Snubbers r

D1.40 Integral Attachment-Note 2 Visual, VT-3 Relief Request 15I-005 Spring Type Supports D1.50 Integral Attachment-Note 2 Visual, VT-3 Rellef Request 151-005 Constant Load Type Supports 01.60 Integral Attachment-Note 2 Visual, VT-3 Relief Request 15I-005 Shock Absorbers l

NOTES:

sol The system neoadery ene.d. en se e 4 saceedias the sies meem.sey caosed v.we ee v. eve cap.bie es set

.iec cessene. eegee,e4 le p3rform the safety-fetaled system foncteen (2)

See secteen 4 el this report tetted "Inserv6ce Gaspect6en of Oess 3 Compements* Ser categeeasettom el FWD 6atogest attachenents.

54FSP 49/101445 25 67

13 YEAR INSERVICE INSPECTION P REV 1 LOUISI ANA POWER AND LIGli WATERFORD STEAM ELECTRIC STATION (MIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CIASS 1, 2, AND 3 CORPONENTS EXAMINATION CAltGORY D-R TOTAL

[AAMINATION ITEM 90.

AREAS EXAMIK D PER ITEM K itt)O REl.IEF/C M NTS D2.10 Pressure Retalning Components Note 1 Visual, VT-2 Pressure Retaining Components Note 1 Visual, VT-2 D2.20 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 Component Supports and Restraints D2.30 Integral Attachment-Note 2 Visual, VT-3 Relief Request 15I-005 Mechanical and Hydraulle Snubbers D2.40 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 Spring iype Supports D2.50 Integral Attachment-Note 2 Visual, VT-3 Relief Request 15I-005 Constant Load Type Supports D2.60 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 Shock Absorbers 1

l NOTES:

ei The syst.= b ada<v..i. ads., e. and eacs.d.as in. sense

,=eny ca...e veev..e vehr. capabe..e..i

.iec es

......d

e. p.,s the sat.tv-4.e.d ey i-s. ace a s23 s secu.a 4.e sh re i.p.4 sa,vece sa.p.co

. o..

3 c ass e., cas.o.res of swo eases,en etischm.ats 4

5478P 49/10 8445-26 68 l

13 YEAR INSERVICE INSPECTION P V1 LOUISIANA PONER AND LIQlT WATERFORD STEAM ELECTRIC STATION UNIT ND. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2 AND 3 COIFONENTS EXAMINATION CATEGORY D-C TUTAL EKAMINATION ITEM W.

AREAS EXAMIBED PER ITEM K itE10 RELIEF /CO M NTS D3.lO Pressure Retalning Components Note 1 Visual, VT-2 Pressure Retalning Components Note 1 Visual, VT-2 03.20 Integral Attachment-Note 2 Visual, VT-3 Rellef Request 151-005 Component Supports and Restraints D3.30 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 IIechanical and Hydraulic Snubbers D3.40 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 Sprlog Type Supports D3.50 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 Constant Load Type Supports D3.60 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 Shock Absorbers NOTES:

s s.ca e.e in r.

i...e e.co.d s in.

e===.a ca e

'v. = *.'-. c.p.6'..'..'.=.ac c' w.

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.es.ch 5478e49/I08 45 27 i

69

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 i

O 5.0 INSERVICE INSPECTION OF SUPPORTS (IWF) 1 Based on Table IWF-2500-1, the examination categories and items identified in the Examination Table are subject to examination under j

LP&L's Inservice Inspection Program. The total numbers of items on the j

table reflect the totals of the Class 1, 2 and 3 supports.

i i

t 5.1 Examination Table and Figure f

i d

j J

a n

f i O i

+

1

(

1 l

I l

I l

4 i

4 4

i i

i h

I i

{

W340076E 70 L

10 YEAR INSERVICE INSPECTION V1 LOUISIANA P(RIER AND LIGIT WIATERFORO STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAW FOR CLASS 1, 2, AND 3 COIFONENTS EXAalf NAT ION Calf CoRY F-A EXAMINATI(RI ITEN El.

AREAS EXAMIDED KTM RELIEF /rnamerwis F1.10 blechanical Connect ions to Pressure Visual, VT-3 Fig IF l

Retalning Components and Building Structure F1.20 Neld Connections to Building Structure Visual, VT-3 Fig IF i

l l

F1.30 Neld and Reechanical Connections at Visual, VT-3 Fig IF Intermediate Joints in Multiconnected i

Integral and Nontntegral Supports Fl.40 Component Displacement Settings of Visual, VT-3 Fig IF j

Guides and Stops. Nisalignment of Supports, Assembly of Support Items i

1 i

5 1

W

)

i TOTAL OF 24 $UPPORTS S478P88/90140S 28 i

i I

71

l 13 YEAR INSERVICE INSPECTION V1 LOUISI ANA PGu[R Ale LIGIT WATERFORD STEA5 ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM IDR CLASS 1. 2. AND 3 CORPONENTS EXAMINATION CAI[GDRV F-8

[XABINATION ITEM IG.

ARE AS EXAGIIED Kilep RELIEF /CMNTS F2.lO IIechanical Connecttons to Pressure Retalning Components and Building Structure F2.20 Weld Connections to Building Structure i

j F2.30 Weld and IIechanical Connect ions at Intermediate Joints in laulticonnected Integral and Nontntegral Supports F2.40 Component Displacement Settings of Guldes and Stops. Nisalignment of Support. Assembty of Support Itens i

j E

j 1

I l

i 1

i 1

TOTAL OF 0 SUPPORTS 547sP 4e/10:445-2e i

I l

77

13 YEAR INSERVICE INSPECTION P V1 LOUISI ANA POWER AND LIGiT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CtASS 1, 2, AND 3 Cour0NENTS EXAMINATION CATEGORY F-C EXABINATI(NI ITEM NO.

AREAS EXAMIE D KTHOD RELIEF /rflamFNTS F3.10 Mechanical Connecttons to Pressure Visual, VT-3 Re11ef Request 15I-006 ISI-OO7, 151-006 Retalning Components and Bullding 15I-009, and ISI-010/ Fig IF l

Structure F3.20 Weld Connect ions to Building Structure Visual, VT-3 Relief Request ISI-OO6, ISI-OO7, 151-006, 15I-009, and ISI-OlO/ Fig IF F3.30 Weld and Mechanical Connections at Visual, VT-3 Relief Request 151-006 1S1-007 ISI-OO8, Intermediate Joints in Mult1 connected 15I-009, and ISI-OlO/ Fig IF Integral and Non1ntegral Supports F3.40 Component displacement settings of Visual, VT-3 Rellef Request 151-006, 15I-007, 151-006, Guides and Stops, Misalignment of 151-009, and ISI-010/ Fig IF Supports, Assemb1y of Support Itens F3.50 Spring Type Supports, Constant Load Visual, VT-4 Type Supports, Shock Absorbers, Hydraulic and Mechanical Type Snubbers i

TOTAL OF 1430 SUPPORTS scree menoises-so 73 4

10 YEAR INSERVICE INSPECTION PROGRAM sev.i FIGURE IF O

Supporting Pressure Ratoining Structure Component m-

.w>

i integral or Nonintegrat Support

)

,s ll 4l o

u Exam. Boundary I

i I

O TYPICAL SUPPORT EXAMINATION BOUNDARY 74

i '

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 I

i l

.f O

6.0 INSERVICE TESTING OF PUMP AND VALVES The Pump & Valve Inservice Test Plan and all Relief Requests associated

]

with those tests are being conducted under the LP&L Pump and Valve Inservice Testing Program which was submitted previously (submitted to NRC via letter NO. W3P84-3473 dated 1/11/85).

E

- O

'T f

4 4-O k.

W340076E 75

__....__.;._.~.__..~-.._.____.._......__-.__......._.___-.__.

10 YEAR INSERVICE INSPECTION PROGRAM l

Rev. 1

O 7.0 RELIEF REQUESTS Louisiana Power and Light requests that relief be granted from ASME Section XI requirements pursuant to Section 50.55a(g)(6)(1) of 10CFR50.

The following Relief Requests document the areas where full compliance with Section XI requirements is not practical /possible during Inservice Examinations. Additional Relief Requests may be generated during the I

service life of the unit, as needed.

RELIEF REQUEST DESCRIPTION ISI-001 Partial Examination of Piping Welds ISI-002 Supplemental Examination for IGSCC ISI-003 VT-3 Examinations on Valve Intervals ISI-004 Reactor Coolant Pump Casing Welds ISI-005 Categorization of IWD into IWF ISI-006 Support Access is Completely Blocked by Thermal Insulation ISI-007 Supports are in Fire Seal ISI-008 Supports are in Penetration ISI-009 Support Blocked by Thermal Insulation (Partially)

ISI-010 Support Blocked by Fire / Heat Insulation l

O W340076E 76 L

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 A.

Subject Request for Relief No. ISI-001 Pg. 1 of 2 4

B.

Component Classification Class 1 and 2 i

Code Examination Category B-J, C-F (All items)

C.

Examination Requirement Category B-J - A surface exam of the 0.D. and volumetric examination of the lower one-third of the weld and HAZ is required for all piping 4" nominal pipe size and greater. A surface examination is required for pipe less than 4" pipe diameter.

Category C-F - Surface and volumetric examination of circumferential and longitudinal butt welds for all piping greater than 4" nominal pipe size with a wall thickness greater than 0.5".

A surface examination only is required for all piping greater than 4" nominal pipe size with a wall thickness of 0.5" or less.

D.

Relief Requested Louisiana Power and Light is requesting that relief be given in reference to obtaining 100% coverage when examining certain items scheduled in IWB-2500-1 (Cat.

B-J) and IWC-2500-1 (Cat. C-F).

E.

Basis for Relief The design of Class 1 and 2 piping systems have welded joints such as pipe to elbow and pipe to component which physically obstruct all or part of the required Section XI examinations from the elbow or component side of the weld.

Partial examinations are done whenever full coverage is not possible. Alternate analyses, search units, vee paths and other techniques will be used to provide additional coverage. During PSI, Louisiana Power and Light generated a detailed summary of the ASME Class 1 and 2 piping system welds that received limited or partial examination. The Summary Report identifies the specific weld, the corresponding isometric drawing, the required examination method, the specific cause for the partial examination, the region of the weld which

\\

can actually be examined and alternative examinations employed (if any).

t l

l l

l W340076E 77 i

l t

10 YEAR INSERVICE INSPECTION PROGRAM Rev. I Relief Request ISI-001 gy Pg. 2 of 2 E. (cont'd)

This Summary Report is contained in the Preservice Report and will be used during the first Interval as a reference for partially examined welds.

Louisiana Power and Light has determined that the partial examinations to be Performed, the examinations performed during fabrication, and the periodic hydrostatic test to be performed will demonstrate an acceptable level of structural integrity.

i F.

Schedule for Implementation First 10 year Interval O

i j

W340076E 78

_ _ = -

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1

-s A.

Subject Request for Relief No. ISI-002 Pg. 1 of 2 B.

Component Classification Class 2 Code Examination Category C-F C.

Examination Requirement A surface examination is required for piping with a wall thickness of 0.5" or less. The examination shall be done to the extent and frequency as specified in IWC-2500-1 (Cat. C-F).

D.

Relief Requested

{

Perform ultrasonic examinations on 10% of the welds on certain Safety 1

Injection and Containment Spray lines in lieu of the surface examinations required by IWC-2500-1 (Cat. C-F).

j E.

Basis for Relief During PSI, members of the NRC staff expressed concern to Louisiana Power and Light personnel that strict compliance with Section XI did not adequately address the issue of Intergranular Stress Corrosion Cracking (IGSCC) for much of the piping susceptible to this condition. Therefore, 1

a l

LP&L opted to select approximately 10% of the welds in certain suction lines of Safety Injection and Containment Spray systems for ultrasonic i

j examinations in lieu of surface examinations. Every effort was made to i

select a representative cross-section of weld types with particular emphasis placed on areas where structural discontinuities were present.

i i

4 i

W340076E 79

= _ _ _.

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 Relief Request ISI-002 Pg. 2 of 2 i

E.

(cont'd)-

The following is a list of all lines which are selected for this program:

2SIl0-5B 2SI24-2A 2SIl0-16B 2SI20-4A 2SI1O-15B 2SI14-23A 2SI14-23B 2CS14-2A 2CS14-2B 2SIl0-5A 2SI20-4B 2SIl0-15A 2SIl0-16A 2 Silo-15 A/B 2SI24-2B 2SI24-3B F.

Schedule for Implementation First 10 year Interval 4

)

i i

j i

i i

t i

i i

i W340076E 80 a

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 A.

Subject p

Request for Relief No. ISI-003 Pg. 1 of 1 B.

Component Classification Class 1 Code Examination Category B-M-2 (Item B12.50)

C.

Examination Requirement A VT-3 internal examination shall be performed on one valve within each group of valves each Inspection Interval.

i D.

Relief Requested Relief is requested to defer the required internal examination on valves bodies which exceed 4" nominal pipe size until maintenance / disassembly is required.

E.

Basis for Relief The Code requirement to disassemble one valve from each design group for the purpose of visual examinations has a small potential for identification of service V

induced flaws or degradation. The industry performance of these valves has proved their excellent ability to resist service degradation or flawing. The inappropriate balance of potential flaw detection and the large impact on expenditures of manpower without substantially increasing component reliability is considered impractical. Also, the substantial expenditures of man-rem without increasing component integrity is undesirable due to ALARA concerns. As an alternative, these examinations will be performed when disassembly is required for maintenance purposes, but not more than once per Inspection Interval.

LP&L has determined that delay of these examinations until maintenance is performed will not affect the function or integrity of these components.

F.

Schedule for Implementation First 10 year Interval O

W340076E 81

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 A.

Subject Request for Relief No. ISI-004 Pg. 1 of 2 B.

Component Classification Class 1 C.

Examination Requirement 1.

Table IWB-2500-1, Category B-L-1, Item B12.10-All pressure retaining welds for one pump from each group of pumps performing a similar function in a system shall receive 100% volumetric examination.

2.

Table IWB-2500-1, Category B-L-2, Item B12.20-The internal pressure boundary surface of one pump from each group of pumps performing a similar function in a system shall receive 100%

visual (VT-3) examination.

D.

Relief Requested 1.

Total relief from the volumetric examination of C.1 above is requested (See Alternate Exams).

2.

Relief from the frequency and extent of visual examination of C.2 above is requested (See Alternate Exams).

E.

Alternate Exams 1.

In lieu of volumetric examination:

100% visual (VT-1) examination of the external surface (s) of all pressure retaining welds shall be performed to the extent and frequency of Table IWB-2500-1, Category B-L-1, Item B12.10.

2.

In lieu of 100% visual examination:

In the event that pump disassembly is required for maintenance purposes,100% visual (VT-3) examination of the accessible internal surfaces of all pressure retaining welds shall be performed to the extent and frequency of Table IWB-2500-1, Category B-L-2, Item B12.20.

W340076E I

82 l

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - I

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 Relief Request ISI-004 V

Pg. 2 of 2 F.

Basis For Relief The pump casings are fabricated with SA-351 CF8M austenitic stainless steel castings using type 308 filler metal which contains 5 to 25 percent and 5 to 18 percent delta ferrite respectively. The presence of delta ferrite provides resistance to IGSCC and improves pitting resistance. To date, the pump manufacturer and the NSSS supplier report no documented instances where repairs to pump casings were necessitated by pump casing material failure or unacceptable volumetric examination results. Therefore, volumetric examination provides little or no additional safety margin.

The duplex microstructure of the austenitic pump casing and weld metal prevents performance of meaningful ultrasonic (UT) examination. Even when using state of the art UT examination techniques, indications are effectively masked by the " noise" created from the microstructure. UT is not an acceptable method for volumetric examination.

To perform radiographic examination, complete disassembly of the pump is required. There is no requirement to disassemble the pump for any scheduled normal maintenance.

Industry experience indicates a very low probability of complete disassembly for non-routine maintenance. Should pump disassembly be performed solely for the purpose of radiographic examination, the potential for substantial man-rem exposure is high. The man-hours expended in pump disassembly / assembly and the accompanying man-rem exposure will not provide any additional safety margin and therefore constitutes undue hardship.

The alternate examinations proposed represent the most reasonable and mean-ingful technique considering the low potential for problems. A surface exam method (dye penetrant) was considered but extensive prepara tion of the as cast pump surface is required with no significant increase in the likelihood that indications would be revealed. The system leakage test and system hydrostatic test required by IWB-2500-1, Category B-P, Items B15.60 and B15.61 respectively provide further assurance of pressure boundary integrity.

G.

Schedule for Implementation First 10 year Interval W340076E 83

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1

()

A.

Subject Request for Relief No. ISI-005 Pg. 1 of 1 B.

Component Classification Class 3 Component Supports C.

Examination Requirement Table IWD-2500-1 requires visual (VT-3) examination of support integral attachments. Paragraph IWF-2510 requires examination of supports of components required to be examined under IWD.

Figure IWF-1300-1 establishes IWD and IWF examination boundaries.

D.

Relief Requested Relief is requested from the examination boundaries of Figure IWF-1300-1 for supports addressed by C above.

E.

Basis for Relief

()

In lieu of the examination boundaries of IWF-1300-1, the entire support, including the integral attachment, is classified as an IWF support examination boundary (see sketch on Attachment 1).

This does not affect the number of supports selected, the examination method or the extent of the examination. However, categorization and scheduling is performed under the requirements of one Article (IWF-2000) negating the undue hardship of implementing both Subsections IWD and IWF.

F.

Schedule for Implementation First 10 year Interval O

W3'30076E 84

~

10 YEAR INSERVICE INSPECTION PROGRMI Rev. 1 Relief Request ISI-005 Pg. 1 of 1 PRESSURE SUPPORTING RE TAINING STRUCTURE COMPONENT

'W

.v INTEGRAL SUPPORT Ii

)

l

{

i I

A s -

IWF EXAM BOUNDARY-IWD EXAM BOUNDARY IWF-13OO-l CODE BOUNDARY PRESSURE SUPPORTING RETAINING STRUCTURE COMPONENT s%-

%w.

INTEGRAL OR NONINTEGRAL SUPPORT J

s -

e e

3

=

=

NEW IWF EXAM BOUNOARY RELIEF REQUEST 005 EXAM BOUNDARY O

l l

W340076E l

85

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 A.

Subject Request for Relief No. ISI-006 Pg. 1 of 1 B.

Component Classification Class 3 Component Supports C.

Examination Requirement Table IWF-2500-1, Category F-C, Items F3.10 through F3.40 - Mechanical connections to pressure boundaries and building structures, weld connections to building structures, weld and mechanical connections at intermediate joints and support assembly and alignment shall be 100% visual (VT-3) examined.

D.

Relief Requested Total relief from the visual examination of C above is requested for the supports listed in Attachment 1.

E.

Basis for Relief Component support access is completely blocked by permanent non-removable insulation. Supported lines operate at temperatures substantially below ambient and are, therefore, subject to severe condensation. The type of insulation used has a permanently sealed vapor barrier to exclude moisture, and removal of the 1

insulation in the support area results in vapor contamination of the surrounding insulation. Possible alternate removable type vapor barrier insulation is not acceptable due to fluoride / chloride content. The requirement for a vapor barrier necessitates non-removable insulation. During the construction phase, examinations were conducted to verify acceptability of the entire component support installation in accordance with the applicable construction codes.

Examination records are on file by suppc,rt number.

F.

Schedule for Implementation First 10 year Interval f

O W340076E 86

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 Relief Request ISI-006 (D

\\_,/ Pg. 1 of 1 Component (s) - Supports listed below System (s) - Chilled Water (AC) i Relief - Inaccessibility - Restraint access completely blocked by permanent thermal insulation.

Support No.

Line No.

Code Class ACR-513 3AC8-7A, 14A 3

ACR-515 3AC8-7A, 14A 3

ACR-1034 3AC10-15A 3

ACR-561 3AC6-28B, 29B 3

ACR-563 3AC6-28B, 29B 3

ACR-551 3AC6-40A 3

ACR-408 3AC6-41A, 42A 3

ACR-410 3AC6-41A, 42A 3

ACR-419 3AC6-41A, 42A 3

ACR-1036 3AC6-42A 3

ACR-1131 3AC6-43B 3

ACR-523 3AC6-52A 3

ACR-522 3AC6-53A 3

ACR-1058 3AC6-40A 3

l ACR-570 3AC6-43B 3

ACR-1087 3AC6-40B 3

O W340076E-87 f

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 A.

Subject

~(

Request for Relief No. ISI-007 Pg. I of 1 B.

Component Classification Class 2 and 3 Component Supports C.

Examination Requirement Table IWF-2500-1, Category F-C, Items F3.10 through F3.40 - Mechanical connections to pressure boundaries and building structures, weld connections to building structures, weld and mechanical connections at intermediate joints and support assembly and alignment shall be 100%

visual (VT-3) examined.

D.

Relief Requested Total relief from the visual examination of C above is requested for the supports listed in Attachment 1.

E.

Basis for Relief l

Component supports are in penetrations which are closed off by permanently installed fire seals. Fire seal material is pumped into the penetration in semi-liquid state and solidifies into a non-removable mass. Fire seal integrity is a Limiting Condition for Operation as identified in W-3 Technical Specification paragraph 3.7.11.

This constitutes undue hardship in conducting exams.

During the construction phase, examinations were conducted to verify acceptability of the component support installations in accordance with the applicable construction code (s).

Examination records are on file by support number.

F.

Schedule for Implementation First 10 year Interval O

I W340076E 88

10 YEAR INSERVICE [NSPECTION PROGRAM Rev. 1 Relief Request ISI-007 Pg. 1 of 1 Component (s) - Supports listed below System (s) - Chilled Water (AC), Component Cooling (CC) i Relief - Inaccessibility - Restraint in penetration with permanent fire seal.

Support No.

Line No.

Code Class ACR-413 3AC6-41A 3

ACR-600 3AC6-41B 3

ACR-412 3AC6-42A 3

i ACR-601 3AC6-42B 3

!i CCRR-781 3CC20-2B 3

j CCRR-712 3CC20-3B 3

f CCRR-932 3CC6-6A 3

CCRR-465 3CC6-71A 3

CCRR-471 3CC6-71A 3

CCRR-119 3CC10-83A 3

CCRR-1072 3CC6-106A 3

{

CCRR-1111 3CC6-106A 3

l CCRR-1091 3CC6-106B 3

l CCRR-37 3CC6-144A/B 3

CCRR-420 3CC16-202B 3

j CCRR-1121 3CC10-289A 3

CCRR-1122 3CC10-290B 3

CSRR-361 2CS10-7B 2

CSRR-372 2CS10-9B 2

i l

CSRR-334 2CS10-11A 2

SIRR-391 2SI8-113RLIA 2

SIRR-939 2SI8-130RL2A 2

4 CCRR-621 3CC16-203A 3

FWRR-262 3FW4-76A 3

1 89 I

W340076E

~.

10 YEAR INSERVICE INSPECTION PROGRAM Rev. I 1

al A.

Subject

()

l Request for Relief No. ISI-008 Pg. 1 of 1 r

B.

Component Classification Class 3 Component Supports 1

C.

Examination Requirement Table IWF-2500-1, Category F-C, Items F3.10 through F3.40 - Mechanical connections l

to pressure boundaries and building structures, weld connections to building I

structures, weld and mechanical connections at intermediate joints, and support j

assembly and alignment shall be 100% visual (VT-3) examined.

D.

Relief Requested i

)

Total relief from the visual examination of C above is requested for the supports listed in Attachment 1.

I E.

Basis for Relief q

Component supports are in penetrations such that supports are completely 4

(

inaccessible for examination. During the construction phase, examinations were conducted to verify acceptability of the component support installations in accordance with the applicable construction code (s).

Examination records are on i

file by support number.

F.

Schedule for Implementation f

i First 10 year Interval.

i i

t l

1 i O W340076E 90

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 Relief Request ISI-008 Pg. 1 of I Component (s) - Supports listed below System (s) - Chilled Water (AC) and Component Cooling (CC)

Relief - Geometric Inaccessibility - Restraint in Penetration.

Support No.

Line No.

Code Class ACR-586 3AC6-41A 3

ACR-587 3AC6-42A 3

CCRR-715 3CC20-2B 3

CCRR-526 3CC20-107A 3

CCRR-445 3CC20-201B 3

O O

W340076E 91

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 A.

Subject (h

(_,)

Request for Relief No. ISI-009 Pg. 1 of 1 B.

Component Classification Class 3 Component Supports C.

Examination Requirement Table IWF-2500-1, Category F-C, Items F3.10 through F3.40 - Mechanical connections to pressure boundaries and building structures, weld connections to building structures, weld and mechanical connections at intermediate joints and support assembly and alignment shall be 100% visual (VT-3) examined.

D.

Relief Requested Partial relief is requested for the supports listed in Attachment I where the supports connect to the pressure boundary.

E.

Alternate Exams The accessible portions of the affected supports are examined to the frequency and extent specified in IWF-2500-1 and IWF-2510.

F.

Basis for Relief Component support access is partially blocked by permanent non-removable insula-tion. Supported lines operate at temperatures substantially below ambient and are, therefore, subject to severe condensation. The type of insulation used has a permanently sealed vapor barrier to exclude moisture, and removal of the insulation in the support area results in vapor contamination of the surrounding insulation.

Possible alternate removable type vapor barrier insulation is not acceptable for use due to high flouride/ chloride content. The requirement for a vapor barrier seal necessitates non-removable insulation.

During the construction phase, examinations were conducted to verify acceptability of the entire component support installation in accordance with the applicable construction codes. Exam nation records are on file by support number.

G.

Schedule for Implementation

/,s'

(_,)

First 10 year Interval.

W340076E 92

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 l

Relief Request ISI-009 Pg. 1 of 4 Component (s) - Supports listed below System (s) - Chilled Water (AC)

Relief - Partial Inaccessibility - Restraint access partially blocked by permanent thermal insulation.

Support No.

Line No.

Code Class ACR-453 3AC6-1A/B 3

ACR-442 3AC6-1A, 78, 14B 3

(

ACR-459 3AC6-1A, IA/B, 2B, 19A, 3

1 198. 19A/B ACR-445 3AC6-1B 3

4 ACV-446 3AC6-1B 3

j ACH-475 3AC6-1B 3

ACR-457 3AC6-2A/B, 19A/B 3

i ACR-462 3AC6-2A, 2B, 19A, 19B 3

ACR-444 3AC6-2A, 2A/B, 14B 3

2 19A, 19A/B ACR-444 3AC6-278, 928 3

ACR-444 j

3AC10-6A, 6B, 15A, ISB 3

j ACH-463 3AC6-2B, 19B 3

j ACR-1041 3AC10-6A 3

ACR-1042 3AC10-6A 3

{

ACR-1064 3AC10-6B 3

l, ACR-455 3AC8-7A 3

i ACH-639 3AC8-7A 3

i ACR-512 3AC8-7A, 14A 3

l ACR-514 3AC8-7A, 14A 3

ACH-640 3AC8-7A, 14A 3

ACH-534 3AC6-78 3

ACR-476 3AC6-78, 14B 3

ACR-497 3AC6-7B, 148 3

i ACR-499 3AC6-78, 14B 3

ACR-535 3AC6-7B, 14B 3

ACR-536 3AC6-7B, 148 3

i W340076E 93

10 YEAR INSERVICE INSPECTION PROGRAM Rev. I i

j Relief Request ISI-009

)

6 Pg. 2 of 4 i

Support No.

Line No.

Code Class l

ACR-454 3AC8-14A 3

[

' ACR-533 3AC6-14B 3

ACR-1040 3AC10-15A 3

j ACH-460 3AC6-19A/B 3

l ACR-452 3AC6-19A/B, 22A/B 3

ACR-470 3AC6-21A 3

ACR-450 3AC6-21A/B 3

j ACR-471 3AC6-20B 3

l ACR-443 3AC6-22A 3

ACR-458 3AC6-22A 3

j ACV-472 3AC6-22A 3

ACR-480 3AC6-22A 3

ACV-447 3AC6-22A/B 3

l ACR-448 3AC6-22A/B 3

ACR-449 3AC6-22A/B 3

ACV-451 3AC6-22A/B 3

i ACR-1100 3AC6-22A/B 3

ACR-441 3AC6-22B 3

i ACV-473 3AC6-22B 3

ACR-474 3AC6-22B 3

)

}

ACR-478 3AC6-22B 3

ACR-479 3AC6-22B 3

j ACR-516 3AC6-OSA, 29A 3

ACR-517 3AC6-28A, 29A 3

ACR-540 3AC6-28B, 29B 3

j ACH-541 3AC6-28B, 29B 3

l ACR-543 3AC6-288, 29B 3

4 ACR-544 3AC6-28B, 29B 3

ACR-560 3AC6-28B, 29B 3

ACR-562 3AC6-28B, 29B 3

ACR-564 3AC6-28B, 29B 3

i ACR-565 3AC6-28B, 29B 3

j ACR-566 3AC6-28B, 29B 3

W340076E 94

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 Relief Request ISI-009 Pg. 3 of 4 l

Support No.

Line No.

Code Class ACH-542 3AC6-29B 3

ACR-1093 3AC6-29B 3

ACR-550 3AC6-40A, 53A 3

ACR-568 3AC6-40B 3

ACR-1088 3AC6-40B 3

ACR-569 3AC6-40B, 43B, 49B 3

ACR-406 3AC6-41A, 42A 3

ACR-407 3AC6-41A, 42A 3

ACR-409 3AC6-41A, 42A 3

ACR-417 3AC6-41A, 42A 3

ACR-421 3AC6-41A, 42A 3

i ACR-435 3AC6-41A, 42A 3

ACR-1027 3AC6-41B 3

ACR-425 3AC6-41B, 42B 3

O ACR-426 3AC6-41B, 42B 3

ACR-427 3AC6-41B, 42B 3

ACR-431 3AC6-41B, 3

ACH-432 3AC6-41B, 42B 3

ACR-422 3AC6-42A 3

ACR-430 3AC6-42A 3

ACH-434 3AC6-42A 3

ACR-1037 3AC6-42A 3

ACR-428 3AC6-42B 3

1 ACR-429 3AC6-42B 3

1 ACR-1019 3AC6-42B 3

ACR-1060 3AC6-42B 3

ACR-559 3AC6-43A, 209A 3

ACR-589 3AC6-209A, 210A 3

ACH-609 3AC6-43A, 209A 3

ACR-612 3AC6-43A, 209A 3

t ACR-520 3AC6-52A 3

ACR-524 3AC6-52A, 53A 3

ACR-525 3AC6-52A, 53A 3

W340076E 95

~.-

-. =_.

10 YEAR INSERVICE INSPECTION PROGRAM 4

Rev. I j

Relief Request ISI-009 Pg. 4 of 4 l

Support No.

Line No.

Code Class ACR-526 3AC6-52A, 53A 3

ACR-552 3AC6-52A, 53A 3

i ACR-521 3AC6-53A 3

ACR-607 3AC6-209A, 210A 3

ACR-588 3AC6-209A, 210A 3

i ACH-573 3AC6-209B 3

ACR-574 3AC6-209B 3

ACR-595 3AC6-209B 3

4 ACR-596 3AC6-209B 3

ACR-597 3AC6-209B 3

ACR-575 3AC6-209B, 210B 3

ACR-576 3AC6-210B 3

ACR-604 3AC6-210B 3

ACR-605 3AC6-210B 3

ACH-461 3AC6-1A/B 3

ACR-1149 3AC6-1B 3

4 4

1 I

i W340076E i

96

10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 A.

Subject Request for Relief No..ISI-010 Pg. 1 of 1 B.

Component Classification Class 3 Component Supports C.

Examination Requirement Table IWF-2500-1, Category F-C, Items F3.10 through F3.40 - Mechanical connections to pressure boundaries and building structures, weld connections to building structures, weld and mechanical connections at intermediate joints, and support assembly and alignment shall be 100% visual (VT-3) examined.

D.

Relief Requested Partial relief is requested for the supports listed in Attachment I where the supports connect to the building structure.

E.

Alternate Exams l

The accessible portions of the affected supports are examined to the frequency and extent specified in IWF-2500-1 and IWF-2510.

2

{

F.

Basis for Relief Component support access is partially blocked by fire / heat resistant insulation applied to protect supporting structural steel. The insulation is applied by spraying Flamastic or Pyrocrete over a wire mesh support. The insulation solidifies into a non-removable mass approximately 3"-5" thick. Fire barrier integrity is a Limiting Condition for Operation as identified in W-3 Technical I

Specification paragraph 3.7.11.

This constitutes undue hardship in conducting exams.

During the construction phase, examinations were conducted to verify acceptability of the entire component support installation in accordance with the applicable construction codes. Examination records are on file by support number.

l G.

Schedule for Implementation First 10 year Interval.

W340076E 97

1 10 YEAR INSERVICE INSPECTION PROGRAM Rev. 1 i

Relief Request ISI-010 Pg. I of 1 I

i Component (s) - Supports listed below i

System (s) - Component Cooling (CC) l Relief - Partial Inaccessibility - Restraint access partially blocked by permanent

[

A fire / heat insulation.

i Support No.

Line No.

Code Class CCRR-467 3CC6-71A 3

CCRR-468 3CC6-71A 3

CCRR-469 3CC6-71A 3

I CCRR-470 3CC6-71A 3

l CCRR-1068 3CC6-71A 3

l CCRR-529 3CC6-71B 3

CCRR-530 3CC6-71B 3

I l

CCRR-531 3CC6-71B 3

1 i

i L

l t

i I

i 4

i I

P j

i i

i f

4 W340076E i

98