ML20128N789
| ML20128N789 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/28/1985 |
| From: | LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20128N767 | List: |
| References | |
| PROC-850528, NUDOCS 8506030385 | |
| Download: ML20128N789 (83) | |
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P O W E R & L I G H T / New ORL ANE Louish 7o174-6006 9 (5o4]386-2345 EN9sOsN May 28, 1985 W3P85-1298 A4.05 Mr. C. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Knighton:
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 TEN YEAR INSERVICE INSPECTION PROGRAM, REVISION 0
Reference:
License Condition 2.C.5
(,,)
In accordance with 10CFR50.55a(g), " Inservice Inspection Requirements"and License Condition 2.C.5, Louisiana Power & Light Company hereby submits seven (7) copies of the Ten Year Inservice Inspection Program which is prepared in accordance with the ASME Code Section XI, 1980 Edition with Addenda through Winter 1981.
Relief from the testing requirements of Section XI is requested when full compliance with the requirements of the code is not practical.
In such cases, specific information is provided which identifies the applicable code requirements, justification for the relief request, and the testing method to be used as an alternative.
It is hereby requested that the subject Program he approved and the ASME Section XI code relief requested be granted pursuant to Section 50.55a(g)(6)(i) of 10CFR50.
Very truly yours,
"/
W K.W. Cook Nuclear Support & Licensing Manager KWC:BGM:sms Ecclosure 8506030385 850528 r]
DR ADOCK 0500 d
Attachment cc (w/o enclosure):
E.L. Blake, W.M. Stevenson, R.D. Martin, D.M. Crutchfield, J.H. Wilson, NRC Resident Inspectors Office
O 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 Od 2.0 INSERVICE INSPECTION OF CLASS'1 COMPONENTS (IWB) 2.1 Exemptions 2.2 System Pressure Tests 2.3. Examination Table 3.0 INSERVICE INSPECTION OF CLASS 2 COMPONENTS (IWC) 3.1 Exceptions 3.2 System Pressure Tests 3.3 Examination Table 4.0 ' INSERVICE INSPECTION OF CLASS 3 COMPONENTS (IWD) 4.1 Exemptions
-4.2 System Pressure Tests 4.3 Examination Table
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5.0 INSERVICE INSPECTION OF SUPPORTS (IWF) 5.1 Examination Table
.6.0 INSERVICE INSPECTION OF PUMPS AND VALVES (IWP) (IWV) 7.0 RELIEF REQUESTS O
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4 10 YEAR INSERVICE II;3PECTION PROGRAM Rev. 0 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 comme rcial 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 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.
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. O l
1.4 Personnel Qualification Personnel performing non-destructive examinations are qualified with a-written procedure prepsred in accordance with SNT-TC-1A 1980. The certification of personnel currently qualified with a prs > dure prepared in accordance with 1975 edition of SNT-TC-1A is valid until racertification is required. At that time, re-certification 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 delineated in examination tables in subsequent sections.
Specific techniques for performing examinations are as noted below:
1.5.L Ultrasonic Examination Ultrasonic (UT) examination is performed when a volumetric examination is required. The examinations are performed-in accordance with Appendix III of Sectica II and Articles IV and V of Section V, as applicable. A documented evaluation qf 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 I
indication 20% of DAC or greater is recorded and investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity and location of the reflector.
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. O
- 1. 5.~ 1 Cont'd Where acceptance standards for a particular component or examination category are in the course of preparation, the evaluation is 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 s
Section III edition applicable to the construction of the component. All results of evaluations and examinations are
. documented in accordance with Article IWA-6000.
1.5.2. Radiographic Examination Radiographic (RT) examination is used to supplement ultra-sonic examination as required. Procedures used will be as
~()-
specified in Article 2 of Section V.
1.5.3 Magnetic Particle Examinations 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.
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 above, PT is also an acceptable alternative for carbon steel items.
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 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.
1.6 Supplemental Program for Intergranular Stress Corrosion Cracking (IGSCC)
This supplemental program was established by Louisiana Power and Light-in order to address concerns relative to IGSCC 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.
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 O
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 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 volumetrically examined except as restricted by part 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
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lines and the four 8-inch LPSI lines penetrating
,j containment.
1.7.2.2
?.11 circumferential welds on the two 14-inch shutdown cooling lines between the containment inboard and outboard isolation valves are 100 4
percent volumetrically examined except as restricted by part geometry or access.
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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 A
examined by the method specified in Table IWC-2500-1, Category C-F.
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 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 2FW18-40A 2FW20-12A P SFW20-11 2FW18-41B 2FW20-14B 4
P 5FW20-13 P 2SI14-18A P 2SI14-18B 2SI8-138RL2B 2SI8-130RL2A 2SI8-113RLIA 2SI8-122RL1B NOTE - The entire line is included in the augmented program unless noted by a "P" which denotes partial.
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 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-ifications'and USNRC Regulatory Guide 1.83.
1.9 Reactor Coolant Pump Flywheel Examination The Reactor Coolant Pump Flywheel. examination will be performed in accordance with paragrrph 4.4.9 of the Waterford 3 Plant Technical Specifications and USNRC Regulatory Guide 1.14.
1.10~ Mechanical and Hydraulic Snubber Examination All mechanical and hydraulic snubbers are visually examined and
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functionally tested in accordance with paragraph 4.7.8 of the Waterford 3 Technical Specifications. Therefore, snubbers are not included in the scope of the-Inservice Inspection Program.
1.11 Ultrasonic Calibration Standards Existing PSI calibration standards are used for the first 10 Year Interval at Waterford 3.
These standards were uti.11 zed during pre-service and were designed and manufactured to satisfy the intent of Article 5 and Appendices I and III of Section X1, 1974. Modifi -
f cation to or rey acement 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.
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. O O
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 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 Program. 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, j }
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 Plant Quality 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.
The repair program complies with the requirements of Articles IWB, IWC, IWD and IWF-4000.
1.14 Additional Examinations If examinations conducted during Inservice Inspection reveal indications exceeding allowable standards, additional examinations are performed as specified in IWB, IWC and IWF-2430.
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10 YEAR INSERVICE INSPECTION PROGRAM Rev. O O
2.0 INSERVICE INSPECTION C" 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, and any Relief Requests associated with 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-gories of IWB-2500-1. Also, the selection of supports under Article
()
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.
l 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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b 10 YEAR INSERVICE INSPECTION PROGRAM Rev.~ 0 2.2.1 Hydrostatic Test (IWA-5211d)
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 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) l
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After each refueling outage, the Class 1 pressure boundary is subjected to a visual exam (VT-2) with the system (s) at nominal operating pressure. The pressure retaining boundary corresponds to the reactor coolant system boundary with all Class 1 valves in the normal position required for normal reactor startup.
Also, the visual exam (VT-2) extends to and includes the second closed valve at the Class 1 pressure boundary extremity.
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- LOUISIANA P(BIER Am LIGHT WATERFORD STEAM ELECTRIC STATION UNIT ND. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 CEE50ENTS EXAMINATION CATEGORY 8-A susAL EXAMINATI(BI ITEM W.
AREAS EXAMIE D PER ITEM ETMD RELIEF /enamsFNTS B1.10 Shell Welds 81.11 Circumferential 3
Volumetric Bl.12 Longitudinal 9
Volumetric 01.20 Head Welds 81.21 Circumferential 2
Volumetric B1.22 Neridional 10 Volumetric B1.30 Shell-to-Flange Weld 1
Volumetric 01.40 Head-to-Flange Weld 1
Volumetric & Surface B1.50 Repair Welds 81.51 Beltline Region TOTAL OF 26 ITEMS 1
I 6478P.48/960005-1 1
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LOUISIANA P(RIER AM LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS.1, 2. AND 3 CORFONENTS EXAMINATION CATEGORY 8-8 susAL EXABINATI(Bi ITEM 86.
AREAS FIAaRIIED PER ITES ETMID RELIEF /enanFNTS Pressurtzer 82.10 Shell-to-Head Welds 82.11 Circumferential 2
Volumetric B2.12 Longitudinal 4
Volunetr,1c B2.20 Head Welds 82.21 Circumferonttal 82.22 Iterldlonal Steam Generators (Primary Side) 82.30 Head Welds B2.31 Circumferential 10 Volumetric B2.32 Meridional 18 Volumetric 82.40 Tubesheet-to-Head Weld 2
Volumetric Heat Exchangers (Primary Side) - Head B2.50 Head helds 82.51 Circumferential 82.52 Meridional C2.53 Longitudinal Shell (Primary Side)
B2.60 Tubesheet-to-Shell (or Head) Welds B2.61 Tubesheet-to-Shell Welds TOTAL OF 36 ITERIS 5478P4eN-2
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LOUISIANA P(RIER Am LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAE FOR CLASS 1. 2, AND 3 CCe0NENTS EXAMINATION CATEGORY 8-D IUIAL EXABINATIEBE ITER 153.
AREAS EXAMIIED PER ITEM IETHOD RELIEF /enamFNTS Reactor Vessel B3.90 Nozzle-to-Vessel Welds 6
Volumetric C3.100 Nozzle Inside Radius Section 6
volumetric Pressurizer B3.110 Nozzle-to-Vessel Welds -
5 Volumetric 83.120 Nozzle Inside Radius Section 5
Volumetric Steam Generators (Primary Side)
B3.130 Nozzle-to-Vessel Welds 6
Volumetric B3.140 Nozzle Inside Radius Sectton 6
Volumetric Heat Exchangers (Primary Side)
B3.150 Nozzle-to-Vessel Welds C3.160 Nozzle Inside Radius Sectton TOTAL OF 34 ITEMS 547 E N -3
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O LOUISIANA PGUER AND LIGfT MATERFORD STEAR ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION Penemaan FOR CLASS 1, 2. Am 3 COIR 0NENTS EXAMINATION CATEGORY 8-E susAL EXABIIenTION ITO W.
AREAS EXAMISED PER ITEM ETMD RELIEF /ensaarNTS B4.10 Partial Penetration Welds B4.11 Vessel Nozzles
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B4.12 Control Rod De1ve Nozzles 91 V1sual, VT-2 84.13 Instrumentation Nozzles 10 Visual, VT-2 Pressurizer 4
84.20 Heater Penetration Welds 30 Visual, VT-2 i
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4 TM AL OF 131 ITEMS i
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5470P.40450se54 i
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O LOUISIANA P(DER Ate LIGH1 WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1. 2. AND 3 Cor0E NTS EXAMINATION CATEGORY 8-F IUIAL EXAMINATIUM ITEM 90.
AREAS EXAMIGED PER ITEM E Ti(ID RELIEF /C M NTS Reactor Vessel B5.10 Nominal Pipe Size > 4 in.
Nozzle-to-Safe End3 utt Welds B5.20 Nominal Pipe Size < 4 in.
j Nozzle-to-Safe End Butt Welds
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85.30 Nozzle-to-Safe End Socket Welds l
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Pressurizer 85.40 Nominal Pipe Size > 4 in.
Nozzle-to-Safe Endlutt Welds 5
Volumetric & Surface 1
4 85.50 Nominal Pipe Size < 4 in.
Nozzle-to-Safe End Butt Welds I
B5.60 Nozzle-to-Safe End Socket Welds Steam Generator i
1 B5.70 Nominal Pipe Size > 4 in.
Nozzle-to-Safe End7utt Welds B5.80 Nominal P1pe Size < 4 in.
j Nozzle-to-Safe End Butt Welds B5.90 Nozzle-to-Safe End Socket Welds Heat Exchangers 1
B5.100 Nominal Pipe Size > 4 in.
f Nozzle-to-Safe End7utt Welds B5.110 Nominal Pipe Size < 4 in.
l Nozzle-to-Safe End Butt Welds l
B5.120 Nozzle-to-Safe End Socket Welds
- 1 CONTINUED l
i 5470P40s950005 5
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O LOUISIANA POWER AND LIGHT-MATERFORD STEAM ELECTRIC STATION UNIT m. 3 INSERVICE INSPECTION PRG3tas FOR CLASS 1. 2. Am 3 CIM9ENTS EXAMINATION CATEGORY 8-F (continued) sulAL EXABINATIEM ITEN m.
AREAS EXAMIED PER ITEM ETMD RELIEF /rfumFNTS Piping 85.130 Nominal Pipe Size > 4 in.
Dissimilar Metal Butt Welds 15 Volumetric & Surface 85.140 Nominal Pipe Size < 4 in.
Dissimilar Metal Butt Welds 9
Surface B5.150 Disstellar Metal Socket Welds i
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TOTAL OF 29 ITEMS screemseessa-s
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O LOUISIANA P(RER Am LIGIT WATERFORD STEAS ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION Ppnman FOR CLASS 1, 2. Am 3 Cor00ENTS EXAMINATION CATEGORY B-G-1 sUsAL EKANINATIGN ITE7 W.
AREAS EXASIDED PER ITEM ETMD RELIEF /ennetNTS Reactor Vessel B6.10 Closure Head Nuts 54 Surface 86.20 Closure Studs, in place B6.30 Closure Studs, when removed 54 Volumetr,1c & Surface B6.40 Threads in Flange 54 Volumetric B6.50 Closure Washers Bushings 54 Visual, VT-1 Pressurtzer i
B6.60 Bolts & Studs B6.70 Flange Surface, when connection disassembled 86.80 Nuts. Bu;hings, and Washers Steam Generators.
4 i
86.90 Bolts and Studs a
B6.100 Flange Surface, when connection i
disassembled B6.110 Nuts, Bushings, and Washers Heat Exchangers B6.120 Bolts and Studs
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I B6.130 F1ange Surface, when connect 100 disassembled 86.140 Nuts. Bushings, and Washers CONTINUED se7 sees /osomes-7
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LOUISIANA PGdER A m LIGHT WATERFORD STEAM ELECTRIC STATION UNIT hD. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2, AND 3 CORFONENTS EFAMINATION CAkEGORY.B-G-1 (continued)
IUIAL EXAMINATI(D1 ITE'1 W.
AREAS EXABIED PER ITEM ETMD RELIEF /rflamEFNTS Piping B6.150 Bolts and Studs B6.160 Flanga Surface, when connection disassembled B6.170 Nuts. Bushings, and Washers Pumps B6.180 Botts and Studs 4 Pumps Volumetric (64)
B6.190 Flange Surface, when connection 4 Flanges disassembled (64)
Visual, VT-1 B6.200 Nuts Bushings, and Washers 4 Pumps Visual, VT-1 (64)
Valves B6.210 Bolts and Studs B6.220 Flange Surface, when connection disassembled B6.230 Nuts, Bushings, and Washers TOTAL OF 408 ITEMS 547se4emsoess-s
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O LOUISIANA POWER A8E) LIGHT WATERFORD STEAaB ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAE FOR CLASS 1, 2. AND 3 COIF 0E NTS EXAMINATION CATEGORY B-G-2 susAL EXABINATIIDI ITEM NO.
AREAS EXABIE D PER ITEM ETHOD RELIEF /rnamEFNTS Reactor Vessel B7.10 Bolts. Studs, and Nuts l
Pressurtzer B7.20 Bolts, Studs, and Nuts 1
Visual,,VT-1 Manway Steam Generators 87.30 Bolts. Studs, and Nuts 4
Visual, VT-1 Manways Heat Exchangers 87.40 Bolts. Studs, and Nuts Piping B7.50 Bolts. Studs, and Nuts 2
Visual, VT-1 Flanges Pumps B'.GO Bolts. Studs, and Nuts 4 Sets Visual, VT-1 of Seal Bolting Valves 87.70 Bolts. Studs, and Nuts 40 Visual, VT-1 Valves CRD Housings l
B7.80 Bolts. Studs, and Nuts l
TT.TAL OF 51 ITEMS i
l 547E40N-9 L
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. LOUISIANA POWER AW LIGIT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS.1,'2, Am 3 COIFOE NTS EXAMINATION CATEGORY 8-H IUIAL EXAMINATION ITEN W.
AREAS EXAMIE D PER ITEN E TFE]D RELIEF /CO M NTS Reactor Vessel B8.10 Integrally Welded Attachments Pressurtzer B8.20 Integrally Welded Attachments 1
Volumetr,1c or Surface Steam Generator 88.30 Integrally Welded Attachments 2
Volumetric or Surface Heat Exchangers B8.40 Integrally Welded Attachments TOTAL OF 3 ITERIS h
5470P48/050005-10
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O LOUISIANA P(kffR AE LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. A m 3 COW OE NTS EXAMINATIOei CATEGORY 8-J suuAL EXAMINATHBt ITE7 W.
AREAS EXAMIE D PER ITEM ETMD RELIEF /rflgmIFNTS 89.10 NominalPipeSize14in.
89.11 Circumferential Welds 318 Volumetric & Surface Relief Request ISI-OO1 89.12 Longitudinal Welds 64 Volumetric & Surface Relief Request 151-001 89.20 Nominal Pipe Size < 4 in.
B9.21 Circumferential Welds 361 Surface B9.22 Longitudinal Welds 89.30 Branch Pipe Connectton Welds 89.31 Nominal P1pe Size 1 4 in.
7 Volumetric & Surface Relief Request ISI-OOI B9.32 Nominal Pipe Size < 4 in.
13 Surface 89.40 Socket Welds T*.TAL OF 763 ITEMS saraees/osases-si
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O LOUISIANA PGER Am LIGfT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1. 2. A m 3 Cor 0E NTS EXAMINATION CATEGORY B-K-1 sutAL EXAMINATIEBt ITE7 W.
AREAS EXAMIED PER ITEM ETM]D RELIEF /rnsMFNTS Piping 810.10 Integrally Welded Attachments PtEPOS 810.20 Integrally Welded Attachments 4
Volumetric or Surface Valves 810.30 Integrally Welded Attachments TOTAL OF 4 ITElitS 5478P40/060005-12
LOUISIANA PONER AND LIGiT WATERFORO STEAM ELECTRIC STATION UNIT NO. 3 I
INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2 AND 3 COMPOE NTS EXAMIhATION CATEGORY B-L-1 B-L-2 A M 8-5-2 IUIAL EXAMINATI(Ni ITE7 M.
AREAS EXAMIE D PER ITEM ETHOD RELIEF /rfimmsFNTS 1
Pumps B12.10 Pump Casing Welds (B-L-1) 8 Volumetric Relief Request 151-004 B12.20 Pump Casing (B-L-2) 4 Visual, VT-3 Relief Request 1S1-004 Valves B12.30 Valves, Nominal P1pe Size < 4 in.
Valve Body Welds B12.40 Valves. Nominal Pipe Size > 4 in.
Valve Body Welds 812.50 Valve Body, Exceeding 4 in.
Nominal Pipe Size (B-N-2) 22 Visual, VT-3 Relief Request 151-003 TOTAL OF 34 ITEMS 5478P.4SM60005-13
t LOUISIANA POWER AND LIGHT WATERFORD STEAN ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. Am 3 COIF 00ENTS EXAMINATION CATEGORY 8-N-1, 8-N-2. A M 8-N-3 lugAL EL 51NATI(BI ITE7 M.
AREAS EXAMIDED PER ITEM ETMD RELIEF /enaarNTS Reactor Vessel 813.10 Vessel Intertor (B-N-1) 1 Vessel Visual, VT-3 j
Reactor Vessel (PWR) 013.30 Interior Attachments Within Beltline Region (8-N-2) 6 Visual, VT-1 813.31 Interior Attachments Beyond Belt 11ne Region (8-N-2) 9 Visual, VT-3 B13.32 Core Support Structure (B-N-3) 1 Vessel Visual, VT-3 TOTAL OF 17 ITEMS 5478P48/060085-14
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O LOUISIANA POKR AND LIGfT WATERFORD STEAN ELECTRIC STATION UNIT NO. 3 INSSRVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 COIFOK MTS EXAMINATION CATEGORY 8-0 usAL EXAMINATIENG ITE7 W.
AREAS EXAMIE D PER ITEM IET 6 RELIEF /rfiamIFNTS Reactor Vessel 814.10 Welds in CRD Housing (Upper) 32 Volumetric or Surface WeIds in CRD Housing (Lower) 32 Volumetric or Surface T
TOTAL OF 64 ITERIS sernese/osenes-is 9
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O LOUISIANA PKI A8e LIGiT WATERFORD STEAM ELECTRIC STATION RetIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 Cor0NENTS EXAMINATION CATEGORY 8-P susAL EXABINATION ITEN BO.
AREAS EXAMItED PER ITEM ETWD RELIEF /eninFNTS i
Reactor Vessel B15.10 Pressure Retaining Boundary Note 1 Visual. VT-2 B15.11 Pressure Retalning Boundary Note 2 Visual. VT-2 Pressurtzer B15.20 Pressure Retalning Boundary Note 1 Visual VT-2 815.21 Pressure Retalning Boundary Note 2 Visual. VT-2 Steam Generators 015.30 Pressure Retalning Boundary Note 1 Visual VT-2 i
j B15.31 Pressure Retaining Boundary Note 2 Visual, VT-2 Heat Exchangers B15.40 Pressure Retalning Boundary B15.41 Pressure Retaining Boundary Piping B15.50 Pressure Retalning Boundary Note 1 Visual. VT-2 B15.51 Pressure Retalning Boundary Note 2 Visual. VT-2 Pumps B15.60 Pressure Retalning Boundary Note 1 Visual. VT-2 815.61 Pressure Retalning Boundary Note 2 Visual VT-2 Valves 815.70 Pressure Retaining Boundary Note 1 Visual, VT-2 1
^
B15.71 Pressure Retalning Boundary Note 2 Visual, VT-2 NOTES:
14 The pressuse retaking boundary dur6ag the systeen Isakage test shall correspond to the seetter coolant systesus boundary with oil valves in the norsaal posituMa which la regewed for aersaat seacter operateen startup. The VT-2 emesnination shall, however. entend to one lacaude the second closed watwo at the boundary omtremity.
(2)
The pressure reta4ains houndary dorsag the systosa hydrostates test 'shael tactado en Cass I components with the system boundary.
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. O LOUISIANA POWER Am LIGfT WATERFORD STEAA ELECTRIC STATION be6IT ND. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2, AND 3 CIMPONENTS EXAMINATION CATEGWtY B-Q IUIAL EXAMINATIEM ITEN W.
AREAS EXAMIE D PER ITEM IET 6 RELIEF /crianFNTS 816.10 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 k
1 l
1 I
I i
i f
4 TOTAL OF 18,700 ITEMS 1
1 i
5470 PAS /050005-3 7 I,
I
10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 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, and any Relief Requests associated with each ites. All welds whose stress levels exceed that shown in IWC-2500-1 (Cat C-F) are examined. Additional details regarding exemptions and syste:n pressure tests are addressed below.
3.1 Exemptions (IWC)
The following exemptions apply to all applicable categories of..
IWC-2500-1. Also, the selection of s'upports under IWF is affected.
3.1.1,IWC-1220(A): As allowed by this paragraph, all Cimas 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 (4) Four 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-
.~
10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 2CS10-12A 2CC8-88A1 2CS10-12B 2CC8-88A2 2CS6-13A 2CC8-91B1 2CS6-13B 2CC8-91B2 2CS8-14A 2CC10-151A/B 2CS8-14B 2CC10-153A/B 2CS6-15A 2CC8-157Al 2CS6-15B 2CC8-157A2 2CS6-16A 2CC8-158B1 2CS6-16B 2CC8-158B2 2CS6-18A 2FS6-64A/B 2CS6-18B 2SA10-103
3.1.3 'IWC-1220(C)
As allowed by this paragraph, all Class 2 component connections.(including nozzles in vessels and pumps), piping and associated valves, and vessels and their attachments that are 4 inch nominal pipe size and smaller are exempt from this program. This exemption applies to all piping <_ 4" nominal pipe size.
3.2 System Pressure Tests (IWC)
As required by Tables IWA-5210-1 and IWC-2500-1 the system presisure tests described in IWA-5211 are conducted as follows:
O F
W340076E
10 YEAR INSERVICE INSPECTION PROGRAM Rev. O mU 3.2.1 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 O
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.
O W340076E
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LOUISIANA POWER A W LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 i
INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. A m 3 COIFONENTS EXAMINATION CATEGORY C-A l
IUTAL EXAMINATI(NI ITEM NO.
AREAS EXAMIIED PER ITEM IETHOD RELIEF /rflameFNTS i
C1.10 Shell Circumferential Welds 10 Volumetric C1.20 Head Circumferential Welds 4
Volumetric l
C1.30 Tubesheet-to-Shell Weld 4
Volumetric i
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I I
i 1
TOTAL OF 18 ITERIS 5478P.40/060005-18 a
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O LOUISIANA P(BIER Am LIGHT WATERFORD STEAR ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. Am 3 COIFONENTS EXAMINATION CATEGORY C-8 IUsAL EXAMINATION ITEM W.
AREAS EXAMIE D PER ITEN GETHOD -
RELIEF / CORE NTS C2.10-Nozzles in Vessels <-1/2 in.
Nominal Thickness -
C2.11 Nozzle-to-Shell (or Head) Weld C2.20 Hozzles Without Reinforcing Plate in Vessels > 1/2 in. Nominal Thickness C2.21 Nozzle-to-Shell (or Head) Weld 4
Volumetric & Surface C2.22 Nozzle Inside Radius Section 4
Volumetric C2.30 Nozzles With Reinforcing Plate in Vessels > 1/2 in. Nominal Thickness 4
C2.31 Reinforcing Plate Welds to Nozzle and Vessel 8
Surface C2.32 Nozzle-to-Shell (or Head) Welds 1
Inside of Vessel Accessible Inside of Vessel Inaccessible 4
Visual, VT-2 I
l
\\
j l
TOTAL OF 20 ITERIS l
s47ee.4e/oscess-le
LOUISIANA PONER Am LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 Cor 0NENTS
~~ EXAMINATION CATEGORY C-C IulAL EXAMINATION ITEM W.
AREAS EXAMIBED PER ITEM ETW RELIEF /CO M NTS Pressure Vessels-C3.10 Integrally Welded Attachments 8
Surface Piping C3.20 Integrally Welded Attachments 24 Surface 1
Pumps C3.30 Integrally Welded Attachments 6
Surface Valves t
C3.40 Integrally Welded Attachments I
i e
i t
TOTAL OF 38 ITEMS mm.-...
Ct (v
LOUISIANA P(RIER A8e LIGHT WATERFORD STEAM ELECTRIC STATION UNIT ND. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2 AND 3 -COIFONENTS EXAMINATION CATEGORY C-D 1
IUIAL EXAMINATIENS ITEM W.
AREAS EXAMIE D PER ITEM ETWD RELIEF /rfMAEFNTS Pressure Vessels C4.10 Bolts and Studs J
Piping C4.20 Bolts and Studs Pumps C4.30 Bolts and Studs Valves C4.40 Bolts and Studs TOTAL OF 0 ITEMS
.l 5478P.49/050045-21
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O LOUISIAN4 POWER Age LIGIT WATERFORO STEAft ELECTRIC STATION IseIT No. 3 INSERVICE INSPECTION Ponceans FOR CLASS 1, 2. AiW 3 CGIEPONENTS EXABBINATIW8 CATEe0RY C-F TOTAL EXAGIINATION ITEN Be.
AREAS EXAf5IDED PER ITEBI SEETMID REL I EF/rnmearagTS C5.10 Piping Wolds < 1/2 in.
Nominal Wa117hickness i
1 C5.11 Circumferential Weld 503 Surface Relief Request 1SI-001. 151-002 C5.12 Longitudinal Weld 81 Surface C5.20 F1 ping Welds > 1/2 in.
i Nominal Wall Thickness C5.21 Circumferential Weld 229 Volumetric & Surface Re11ef Request 15I-001 C5.22 Longitudinal Weld 30 Volumetric & Surface Relief Request ISI-OO1 C5.30 Pipe Branch Connecttons > 4 in.
Nominal Branch Pipe Size C5.31 Circumferential Weld 3
Surface C5.32 Longitudinal Weld 4
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1 TCTAL OF 846 ITEMS 3
2 5478P.49/060005 -22 i
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O LOUISIANA PONER AND LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. A m 3 CDIFONENTS EXAMINATION CATEGORY C-G I
susAL EKAMINATIGN ITE7 ND.
AREAS EXAMI8ED PER ITERI IETMD RELIEF /rflamFNTS Pumps CG.10 Pump Cas1ng WeIds Valves C6.20 Valve Body Welds 4
Surface 1
TOTAL OF 4 ITERIS 5478P.40/050erS-23
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O LOUISIANA PGdER AND LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 COM OE NTS EXAMINATION CATEGORY C-H 1
u AL EXABINATIEDI ITEN ND.
AREAS EXAMISED PER ITEM ETHOD -
RELIEF /CnemEFNTS 4
Pressure Vessels C7.10 Pressure Retalning Components Note 1 Visual, VT-2 C7.20 Pressure Retalning Components Note 1 Visual, VT-2 Piping C7.30 Pressure Retaining Components Note 1 Visual, VT-2 C7.40 Pressure Retaining Components Note 1 Visual, VT-2 Pumps C7.50 Pressure Retaining 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 i
C7.80 Pressure Retaining Components Note 1 Visual, VT-2 l
4 i
i NOTES:
t (1)
The pressure reteenlas boundary includes only these porteens of the system required to operate er support the safety system t
function up to end lacluding the first normany closed velve (lacauding a safety or reNet velve) er enive capable of esteenets closure when the selety function is required.
'l 1
5478P49/050005-24
10 YEAR INSERVICE INSPECTION PROGRAM Rev. O O
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 IWF, examination of the entire support is required when the components are required to be examined by IWD. The IWD and IWF examination boundaries are specified in Fig. IWF-1300-1.
Ultimately, the rules of the two articles 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 aad the Examination Table). With this approach, all of the required support examinations are performed as required by the ASME code, and i
the process of categorization and scheduling is greatly simplified.
! o 4.1 Exemptions The following exemptions apply to all applicable categories of IWD-2500-1.
Selection of supports under IWF is affected.
f i
4.1.1 IWD-1220.1: As allowed by this paragraph, all Class 3 integral attachments of supports and restraints to components l
that are 4 inch nominal pipe size and smaller except for l
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 Feedwater lines:
O W340076E
10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 EFW SYSTEM ( <4")
Line No.
3FW4-76A 3FW4-77B 3FW4-46 3FW4-47 3FW1 -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:
(A) The components are located in systems (or portions of s
_)
systems).whose function is not required in support of Reactor Residual Heat Removai, Containment Heat Removal, and Emergency Core Cooling.
(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 SCC 18-11A/B)
W340076E
10 YEAR INSERVICE.INSFECTION PROGRAM Rev. 0 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 3CC10-15A1 3FS10-76A/B 3CC10-33B2 3FS10-77A/B 3CC10-78A/B 3FS6-66A/B 3CC,10-57A2 3SI16-41A 3CC6-39A/B 3SI16-41B
(}
3CC6-317 3SI6-46A/B 3CC6-12A/B
~3SI6-47A/B 3CC12-130A/B 3SI6-48A/B
- 3CC10-45A1 3SI6-180A 3CC10-63B2 3SI6-180B 3CC12-371A/B 3CC10-27A2 4.2 System Pressure Tests As required by Tables IWA-5210-1 and IWD-2500-1 the system pressure tests described in IWA-5211 are conducted as follows:
O W340076E
10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 4.2.1 Hydrostatic Testing (IWA-5211d)
The hydrostatic testing requirements of IWD-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 due to repair or replacement activity is handled on a case by case basis.
4.2.2 Inservice Test (IWA-5211c)
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
( }'
boundary extends up to and including the first normally closed valve or valve capable of automatic closure to perform the safety-related system function.
e e
O W340076E
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O LOUISIANA P(RIER A8e LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2 AND 3 COEDENTS EXAMINATION CATEGORY D-A suvAL EKABINATION ITEM IG.
AREAS EXANIE D PER ITEM ETM)D RELIEF /enmIFNTS-l D1.10 Pressure Retaining Components Note 1 Visual, VT-2 Pressure Retaining Components Note 1 Visual, VT-2 D1.20 Integral Attachment-Note 2 Visual, VT-3 Relief Request ISI-005 Component Supports and Restraints DI.30 Integral Attachment-Note 2 Visual, VT-3 Relief Request ISI-005 i
Mechanical and Hydraulic Snubbers D1.40 Integral Attachment-Note 2 Visual, VT-3 Relief Request ISI-OOS l
Spring Type Supports DI.SO Integral Attachment-Note 2 Visual, VT-3 Relief Request 15I-005 Constant Load Type Supports I
DI.60 Integral Attachment-Note 2 Visual, VT-3 Relief Request ISI-005 j
Shock Absorbers i
1 I
l i
4 i
NOTES:
(4 The systeen boundary entends up to and including the twst normeNY closed wahre er valve capatde of automat 6c closure as requ6ted to perform the safety-ratened system funct6on.
(2)
See section 4 of tens report tested " Inservice inspection of Oass 3 Components
- for categorisation of IWO integral
-l attachments.
suse-4emones-as
.O m.
b.
3 LOUISIANA P(MER AM LIGHT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 y INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2, AND 3 COEDENTS EXAMINATION CATEGORY D-B susAL EXAMINATIEN6 ITEM W.
AREAS EXAMIE D PER ITEN ETMD RELIEF /rmRIFNTS 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 ISI-OOS Component Supports and Restraints D2.30 Integral Attachment-Note 2 Visual, \\fT-3 Relief Request ISI-OOS Mechanical and Hydraulic Snubbers D2.40 Integral Attachment-Note 2 Visual, VT-3 Reller Request 151-005 Spring Type Supports D2.50 Integral Attachment-Note 2 Visual, VT-3 Relief Request ISI-OOS Constant Lcad Type Supports D2.60 Integral Attachment-Note 2 Visual, VT-3 Relief Request 15I-005 Shock Absorbers i
t i
i l
NOTES:
(t)
Thy systee boundary entends up to and includsag the first normally closed valve or velve capable of automatic closure es required to perform the sesstreetated system funct6en.
(2)
See Section 4 of this report titled % serv 6ce Inspection of Oess 3 Components" for cologoriset6on of IWD integral attachments.
5478P 48/050005-26
[
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O's
^
LOUISIANA P(NIER AND LIGHT WATERFORD STEAN ELECTRIC STATION UNIT NO. 3
' INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 COMPONENTS EXAMINATION CATEGORY D-C IUIAL EXAMINATIING ITE7 NO.
AREAS EXAMIE D PER ITEM ETHOD RELIEF /enamnFNTS D3.10 Pressure Retaining Components Note 1 Visual, VT-2
~ Pressure Retalning Components Note 1 Visual, VT-2 D3.20 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 Component Supports and Restraints D3.30 Integral Attachment-Note 2 Visual, VT-3 Reller Request ISI-OOS Mechanical and Hydraulic Snubbers D3.40 Integral Attachment-Note 2 Visual, VT-3 Relief Request 151-005 Spring Type Supports D3.50 Integral Attachment-Note 2 Visual, VT-3 Relief Request ISI-OOS Constant Load Type Supports D3.60 Integral Attachment-Note 2 Visual, VT-3 Relief Request ISI-OOS Shock Absorbers NOTES:
(t)
The system boundary entende up to and laciud6ng the first normatey closed valvo or valve capable of eviomatic closwo as regadred to perform the safety-related system function.
(2)
See Section 4 of this report titled "laservice Inspection of Cass 3 Components" for categorizat6on of IWD integral attachments.
547tP49/0500eS-27
10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0
.s 5.0 INSERVICE INSPECTION OF SUPPORTS (IWF)
Based on. Table IWF-2500-1, the examination categories and items identified in the Examination Table are subject to examination under LP&L's Inservice Inspection Program. The total numbers of items on the table' reflect the totals of the Class 1, 2 and 3 supports.
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W3t0076E l.
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O-LOUISIANA POMER AND LIGiT WATERFORD STEAM ELECTRIC STATION UNIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1, 2. AND 3 CO W ONENTS EXAMINATION CATEGORY F-A.
EXAMINATIG4 ITE9 90.
AREAS EXAMIE D ETHOD RELIEF /enimEFNTS F1.10 Mechanical Connecttons to Pressure Visual, VT-3 Retalning Components and Building Structure F1.20 Weld Connections to Building Structure Visual, VT-3 F1.30 Weld and Mechanical Connections at Visual,,VT-3 Intermediate Joints in Mult1 connected Integral and Non1ntegral Supports d
F1.40 Component Displacement Settings of Visual, VT-3 Guides and Stops. Misalignment of Supports, Assembly of Support Itens TOTAL OF 24 SUPPORTS 547se4e/seases-as
p 3
n LOUISIANA P(BIER Ale LIGtT WATERFORD STEAaB ELECTRIC STATION uMIT NO. 3 INSERVICE INSPECTION PROGRAM FOR CLASS 1. 2. AND 3 CDar0K MTS EKAMINATION CATEGORY F-8 EKAMINATION ITEM NO.
AREAS EXAGIIE D GETHOD RELIEF /COIMENTS -
F2.10 Mechanical Connecttons to Pressure Retalning Components and Building Structure i
F2.20 Weld Connections to Building Structure F2.30 Weld and Mechanical Connections at Intermediate Joints in Mult1 connected Integral and Nontntegral Supports F2.40 Component Displacement Settings of Guides and Stops. Misalignment of Support. Assemb1y of Support Itens J
P 1
i TOTAL OF 0 SUPPORTS 547se.4e/oscess-as
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O LOUISI ANA POWER Ape LIGHT WATERFORO STEASI ELECTRIC STATION ImeIT IW. 3 INSERVICE INSPECTION Ponce m FOR CLASS 1, 2 AND 3 CIEFO M NTS EXAIIINATION CATEGORY F-C EXASIINATHBe ITEM 95.
AREAS EXAMIE D HETtWO RELIEF /rneragts F3.10 Mechanical Connections to Pressure Visual, VT-3 Relief Request ISI-006 151-007. ISI-008, Retaining Components and Building ISI-009, and ISI-010 Structure F3.20 Weld Connections to Building Structure visual, VT-3 Relief Request 151-006 ISI-007 ISI-008 ISI-009, and ISI-010 F3.30 Weld and Mechanical Connections at Visual, VT-3 Relief Request ISI-006, ISI-007, 151-008 Intermediate Joints in Multiconnected ISI-009, and ISI-010 i
Integral and Nonintegral Supporta F3.40 Component displacement settings of Visual, VT-3 Relief Request 151-006, ISI-007. ISI-008, Guides and Stops. Misalignment of 151-009, and ISI-010 Supports, Assembly of Support Items F3.S0 Spring Type Supports, Constant Load Visual, VT-4 Type Supports Shock Absorbers.
Hydraulic and Mechanical Type Snubbers I
i i
i i
i a
TUAL OF 1429 SUPPORTS i
547eP 40/060006-30 1
10 YEAR INSERVICE INSPECTION PROGRAM
.~
Rev. 0 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).
4 O
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..W340076E
.. _ _ _. _,,.. _ _ _ _ _... _. _ _ _ _ _.. _. _. _. _.. _ _ _ -. ~ _. _. -... _ - _ _ _ - _ _ _ _ _ _ _ _ _. - -. _ _ _. _..... _
10 YEAR INSERVICE INSPECTION PROGRAM Rev. 0 g s,
(.
~
7.0 RELIEF REQUEST 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 service life of the unit, as needed.
RELIEF REQUEST REVISION DESCRIPTION ISI-001 0
Partial Examination of Piping Welds ISI-002 0
Supplemental Examination for IGSCC ISI-003 0
VT-3 Examinations on Valve Intervals ISI-004 0
Reactor Coolant Pump Casing Welds ISI-005 0
Categorization of IWD into IWF
()
ISI-006 0
Support Access is Completely Blocked by Thermal Insulation ISI-007 0
Supports are in Fire Seal ISI-008 0
Supports are in Penetration ISI-009 0
Support Blocked by Thermal Insulation (Partially)
ISI-010 0
Support Blocked by Fire / Heat Insulation l
t l
l W340076E
R211of R:qu2st.ISI-001 Rev. O Pg. 1 of 2 1
A.
Subject Request for Relief No. ISI-001 Rev. O B.
Component Classification 1
Class 1 and 2
. 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.
r Category C-F Surface and volumetric examination of circumferential and f
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 II examinations from the elbow or component-side of the veld.. Partial
-examinations are done whenever full c~erage is not possible. Alternate analyas.
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 bport 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 pl
~can actually be examined and alternative examinations employed (if any).
[
~W340076E
Ralisf Raqusst ISI-001 Rev. O 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.
F.
Schedule for Implementation First 10 year Interval l
l i
O W340076E
Ralief Rzqusst ISI-002 Rzv. O Pg. 1 of 2 O\\_/I "A.
Subj ect Request for Relief No. ISI-002 Rev. 0 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 Injection and Containment Spray lines in lieu of the surface examinations l
required by IWC-2500-1 (Cat. C-F).
i ()
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, LP&L opted to select approximately 10% of the welds in certain suction lines of Safety Injection and Containment Spray systems for ultrasonie
[
examinations in lieu of surface examinations.
Every effort was made to select a representative cross-section of weld types with particular emphasis placed on areas where structural discontinuities were present.
O W340076E
Ralief Requsst ISI-002 Rsv. O Pg 2 of 2 0
- E. ~(cont'd)
The following is-a list.of all lines which are selected for this program:
i ac 2SI1O-5B 2SI24-2A 2SIl0-16B 2SI20-4A
-2SIl0-15B 2SI14-23A 2SI14-23B 2CS14-2A 2CS14-2B 2SIl0-5A 2SI20-4B' 2SIl0-15A 2SIl0-16A odIl0-15 A/B 2SI24-2B 2SI24-3B F.
Schedule for Implementation First 10 year Interval O
s L-s t'
^
l f
l 1.
W340076E
R211cf Requast ISI-003 Rav. O Pg 1 of 1
- V A.
Subj ect Request for Relief No. ISI-003 Rev. 0
-B.-
Component Classification Class l' 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.
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 o'f visual examinations has a small potential for identification of service induced flaws or degradatioit. The industry performance of these valves has proved their excellent ability to resist service degradstion 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 undesirsble due to ALARA concerns. 'As an I
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 ::hese examinations until maintenance is performed will not affect the function or integrity of these components.
l
.F.
-Schedule for Implementation-First 10 year Interval l
l O
l l
.W340076E v
u
/
Ralief Raqusst ISI-004 Rsv. 0
/-
Pg 1 of 2 A.
Subject Request for Relief No ISI-004 Rev. O j
B.
Component Classification Class 1 C.
Examination Requirement 1
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.
4 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).
t 2.
Relief from the frequency and extent of visual examination of C.2 above is requested (See Alternate Exams).
f i
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 I
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 i
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.
u j_
W340076E
Raliof Rsqusst ISI-004 Rav. O Pg 2 of 2
/s
)
(',/
1 F.
Basis For Relief l
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" creo?ed 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 the're-fore constitutes undue hardship.
The alternste examinations proposed represent the most reasonable and meaningfu1* technique considering the low potential for problems. A surface exa method (dye penetrant) was considered but extensive preparation of the as :ast 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 15.60 and B15.61 respectively provide further assurance of pressure boundary
()
integrity.
G.
Schedule for Implementation First 10 year Interval W340076E
Relisf Rsquaat ISI-005 RIv. O Pg 1 of 1 A.- Subject Request for Relief No. ISI-005 Rev. O 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 Articles IWD and IWF.
F.
Schedule for Implementation First 10 year Interval O
W340076E
Ralief Rzquest ISI-005
, Rev. 0 Page 1 of 1 1
F 1
Pressure Retaining Component s%-
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Boundary M -1300-1 Code Boundary Pressure Retaining Component
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n=14af Raquest 005 Exam Wd=7 4
- O W340076E
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I Ralief Rsqu2st ISI-006 R v. O Pg 1 of 1 A.
Subj ect i
Request for Relief No. ISI-006 Rev. O j
-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 O-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 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 phaset 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.
F.
Schedule for Implementation First 10 year Interval O
'W3&OO76E
1 Ralief Rsquaat ISI-006 Rev. 0 Pg 1 of I Component (s) - Supports listed below System (s) - Chilled Water (AC)'
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 ACR-570 3AC6-43B 3
ACR-1087 3AC6-40B 3
t W340076E
Ralief R:quset ISI-007 Rsv. 0 Pg. 1 of 1 O
A.
Subj ect Request for Relief No. ISI-007 Rev. O 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 assembl'y 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.
o E.
Basis for Relief 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 parap,raph 3.7.11.
This constitutes undue hardship in conducting exams.
l During the construction phase, examinations were conducted to verify j
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
W35.0076E
Ralief Rsqusst ISI-007-Rev. O' Pg 1 of I Component (s).- Supports listed below System (s) - Chilled Water (AC), Component. Cooling (CC)
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-ACR-601 3AC6-42B 3
CCRR-781.
3CC20-2B 3
.CCRR-712 3CC20-3B 3
CCRR-932 3CC6-6A 3
Y 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
CCRR-1091.
3CC6-106E-3 CCRR-37 3CC6-144A/B 3
CCRR-420 3CC16-202B 3
CCRR-1121 3CC10-289A 3
CCRR-1122 3CC10-290B 3
CSRR-361 2CS10-7B 2
'CSRR-372 2CS10-9B 2
CSRR-334 2CS10-11A-.
2 SIRR-391 2SI8-113RLIA 2
SIRR-939 2SI8-130RL2A 2
CCRR-621-3CC16-203A
-3 FWRR-262 3FW4-76A 3
O
.: W340076E -
Relief Raqusst ISI-008 Rsv. O Pg.1 of 1 A.
Subj ect Request for Relief No. ISI-008 Rev. O 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.
O E.
Basis for Relief
\\'>
Component supports are in penetrations such that supports are completely-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 file by support number.
F.
Schedule for Implementation First 10 year Interval.
i i
e
- O W340076E
... ~ -
Ralief Rsqusst ISI-008 Attachment.1 Rev. O Pg 1 of l' 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
0.
'l b
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W340076E
Ralief R:quset ISI-009 Rsv. 0
- ,y Pg 1 of 1 O
A.
Subj ect Request for Relief No. ISI-009 Rev. 0 4
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 bui;licq structures, weld connections to-building 4
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, i
t 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 l
in the support area results in vapor contamination of the surrounding insulation.
f Possible alternate removable type vapor barrier insulation is not acceptable for l
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. Examinatica records are on file by support number.
,(~h
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G.-
Schedule for Implementation First 10 year Interval.
W340076E
B Raliof Rsqusst ISI-009 Rev. 0 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, 7B, 14B 3
ACR-459 3AC6-1A, IA/B, 2B, 19A, 3-19B, 19A/B ACR-445 3AC6-1B 3
ACV-446 3AC6-1B 3
ACH-475 3AC6-1B 3
ACR-457 3AC6-2A/B, 19A/B 3
ACR-462 3AC6-2A, 2B, 19A, 19B 3
ACR-444-3AC6-2A, 2A/B, 14B 3
19A, 19A/B ACR-444 3AC6-27B, 92B 3
ACR-444 3AC10-6A, 6B, 15A, ISB 3
ACH-463 3AC6-2B, 19B 3
ACR-1041 3AC10-6A 3
ACR-1042 3AC10-6A 3
ACR-1064 3AC10-6B 3
ACR-455 3AC8-7A 3
ACH-639 3AC8-7A 3
ACR-512 3AC8-7A, 14A 3
ACR-514 3AC8-7A, 14A 3
ACH-640 3AC8-7A, 14A 3
ACH-534 3AC6-7B 3
ACR-476 3AC6-7B, 14B 3
ACR-497 3AC6-7B, 14B 3
ACR-499
-3AC6-7B, 14B 3
O
^ca-535 3^c6-78. 14=
3 ACR-536 3AC6-7B, 14B 3
j.
'W340076E
Ralisf Rsquast ISI-009 Rev. 0 Pg 2 of 4 Support No.
Line No.
Code Class ACR-454 3AC8-14A 3
ACR-533 3AC6-14B 3
6 ACR-1040 3AC10-15A 3
ACH-460' 3AC6-19A/B 3
ACR-452 3AC6-19A/B, 22A/B 3
ACR-470 3AC6-21A 3
ACR-450 3AC6-21A/B 3
ACR-471 3AC6-20B 3
ACR-443 3AC6-22A 3
ACR-458 3AC6-22A 3
ACV-472 3AC6-22A 3
ACR-480 3AC6-22A 3
?ACV-447 3AC6-22A/B 3
ACR-448 3AC6-22A/B 3
ACR 449 3AC6-22A/B 3
- O icv-451
>>ce-224/>
a ACR-1100 3AC6-22A/B 3
ACR-441 3AC6-22B 3
ACV-473' 3AC6-22B 3
ACR-474 3AC6-22B 3
., ACR-478 3AC6-22B 3
ACR-479 3AC6-22E 3
ACR-516 3AC6-28A, 29A 3
ACR-517 3AC6-28A, 29A 3
L
'ACR-540' 3AC6-28B, 29B 3
l ACH-541 3AC6-288, 29B 3
l ACR-543 3 C6-28B, 29B 3
ACR-544 3AC6-285, 29B 3
ACR-560 3AC6-28B,' 29B 3
ACR-562 3AC6-288, 29B 3
'ACR-564 3AC6-28B,-29B 3
ACR-565' 3AC6-28B, 29B 3
ACR-566~
3AC6-28B, 29B 3
i l
W340076E L
Raliof Requsat ISI-009 Rev. O Pg 3 of 4 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
ACR-435 3AC6-41A, 42A 3
ACR-1027 3AC6-41B 3
ACR-425 3AC6-41B, 42B 3
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
ACR-429 3AC6-42B 3
4 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
ACR-520 3AC6-52A 3
ACR-524 3AC6-52A, 53A 3
'ACR-525 3AC6-52A, 53A 3
ACR-526 3AC6-52A, 53A 3
W350076E
Ralisf Rsqusst ISI-009
_ Rev. 0 Pg 4 of 4 Support No.
Line No.
Code Class ACR-552 3AC6-52A, 53A 3
ACR-221-3AC6-53A 3
ACR-607 3AC6-209A, 210A 3
ACR-588 3AC6-209A, 210A 3
ACH-573 3AC6-209B 3
ACR-574 3AC6-209B 3
ACR-595 3AC6-209B 3
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
C W340076E
Ralief Raquant ISI-010 Rsv. O Pg 1 of 1 A.
Subject Request for Relief No. ISI-010 Rev. 0
.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 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 fire / heat resistant insulation f
applied to protect supporting structural steel.. The insulation is applied by spraying Flamastic or Pyrocrate over a wire mesh support. The insulat' ion 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 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.
G.
Schedule for Implementation First 10 year Interval.
V360076E
~
l R211cf Rsqu2at ISI-010 Attachment i Rev. O Pg 1 of 1 Tl v.'
Component (s) - Supports listed below
' System (s) - Component Cooling (CC)
Relief - Partial Inaccessibility - Restraint access partially blocked by permanent fire / heat insulation.
Support No.
Line No.
Code Class CCRR-467 3CC6-71A 3
.CCRR-468 3CC6-71A 3
CCRR-469-3CC6-71A 3
CCRR-470 3CC6-71A 3
CCRR-1068 3CC6-71A 3
CCRR-529 3CC6-71B 3
CCRR-530 3CC6-71B 3
CCRR-531 3CC6-71B 3
Oc a
I l
f PV i
i s
W340076E
. - -. -