ML19321B315
| ML19321B315 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/25/1980 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19321B311 | List: |
| References | |
| NUDOCS 8007310374 | |
| Download: ML19321B315 (78) | |
Text
O O
JOSEPH M. FARLEY NUCLEAR PLANT UNIT NO. 2 Response to The Provisions of 10 CFR 50.55a(g)
O Inservice Inspection Program for Class 1, 2, and 3 Components 1
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,8007310374 -
TABLE OF CONTENTS 9
1.0 INTRODUCTION
. . . . . . . . . . . . . . . 1-1 2.0 CLASS 1 COMPONENTS . . . . . . . . . . . . . . .2-1 3.0 CLASS 2 COMPONENTS . . . . . . . . . . . . . . 3-1 4.0 CLASS 3 COMPONENTS . . . . . . . . . . . . . . . 4-1 O
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-s 1. 0 INTRODUCTION
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{V 1.1 General This document describes the revised Inservice Inspection Program for the first ten year interval of commercial operation of Farley Nuclear Plant, Unit No. 2.
The original ISI program for Farley-2 was prepared in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1971 Edition through Winter 1971 Addenda for Class 1 components. The Class 2 components were scheduled
~ for examinationLin accordance with the 1971 Edition through Winter 1972 Addenda of Section XI.
This revised ISI program has been upgraded with the intent to meet, as much as practical, the requirements of the 1974 Edition through Summer 1975 Ad-denda of Section XI for Class 1, 2, and 3 components.
1.2 Effective Date This revised ISI plan shall go into effect at the start of the first 120-month interval of plant commercial operation.
1.3 Scope .
Ihis document is a description of the ISI program for Unit 2 of Plant Farley.
p The programs for Class 1, 2, and 3 component examinations are included.
U 1.4 Component Upgrading All plant components have been reviewed to determine the appropriate classifi-cation for inservice inspection. Regulatory Guide 1.26 was used for guidance in determining component classificatior.s.
It must be noted that the classification of components as ASME Class 1, 2, or 3 equivalent for inservice inspection does not imply that the components were designed in accordance with ASME requirements. The component design codes remain as stated in the FSAR.
1.5- Subsequent ISI Plan Revisions
< In accordance with the existing regulations of 10CFR50.55a, the inservice examination program for Class 1, 2, and 3 components will be reviwed near the end of each 120-month ir.terval. At this t W the plan will be modified as required to bring it into compliance with the lastest NRC-approved version y
of Section XI.
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1.6 Responsibility Alabama Power Company bears the overall responsibility for the performance of r"[-
(~/ ~ the inservice examinations. Certain nondestructive examinations will be per- l formed by a qualified examination agency. The results of such examinations i will be reported to Alabama Power Company for final evaluation and disposition. l 1.7 Records Records and documentation of all information and inspection results, which provide the basis for evaluation and which facilitate comparison with results from previous and subsequent inspections, will be maintained and will be avail-able for the active life of the plant in accordance with Section XI, IWA-6000.
1.8 Methods of Examination The method of examination planned for each area is delineated in subsequent sections. Personnel performing NDT examinations will be trained in accordance with the American Society for Nondestructive Testing (ASNT),1975 Edition of
" Recommended Practice SNT-TC-1A, Supplements and Appendices", as applicable for l technique and method used. 1 1.8.1 Ultrasonic Ultrasonic examinations will be conducted in accordance with the provisions 0
()) of Appendix I and Article 5 of Section V as required by Paragraph IWA-2232.
As an alternative to using Article 5 of Section V, Appendix III of Section XI of the 1974 Edition, Winter 1975 Addenda of the ASME Boiler and Pressure Vessel Code will be used as a guide for ultrasonic examination of piping systems.
It is recognized that Appendix III of Section XI was issued in the Winter 1975 Adaenda and, as such, has not been officially recognized by the NRC by refer-ence in 10CFR50. However, Appendix III is the first guideline that has been published in the ASME Codes for the ultrasonic examination of pipe welds and, as such, its use is essential.
1.8.2 Radiographic Radiographic techniques will be used to supplement UT as required.
.. 1.8.3 Liquid Penetrant Dye penetrant examinations will be performed whenever a surface examination is required on non-magnetic piping.
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1.8.4 Magnetic Particle Magnetic particle tests will usually be used when surface examination of car-bon steel components is required.
1.8.5 Visual A visual (VT) examination will be employed to provide evidence of leakage or to provide a report of the general condition of the component.
1.9 Evaluation of Examination Results Articles IWC-3000 and IWD-3000 entitled, " Evaluation of Examination Results" are in the course of preparation by the Code Committee and, as yet, are not available for use. Therefore, the rules of IWA-3000 will be utilized with the exception that the evaluation of any indications detected during any in-service examinations will be made using the acceptance standards for materials
-and welds specified in the code under which the specific component was constructed.
1.10 Repair Procedures Articles IWC-4000 and IWD-4000 entitled, " Repair Procedures" state that the o rules of IWB-4000 shall apply. Where it is considered that the repair pro-Q cedures outlined in IWB-4000 are inappropriate for the Class 2 and 3 compon-ents in this program, the rules of IWA-4000 will be applied.
Modifications, additions, and alterations to systems shall be made in accor-dance with the 1974 Edition of Section XI with Addenda through Summer 1975.
1.11 Limitations of Examinations Limitations may occur for the examination of piping system circumferential butt welds (Categories B-J, C-F, and C-G) when the welds occur at geometric dis-continuities such as pipe-to-vessel welds, pipe-to-fitting welds, or fitting-to-fitting welds. For pipe-to-fitting or pipe-to-vessel nozzle welds, examinations can be performed to the extent required by T-532 of Section V from the weld and pipe surfaces. Examination from the fitting side would be dependent upon the geometric configuration. Where elbows or tees are concerned, examinations can be performed from the. fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling. No examinations can be performed from the fitting side when it is a valve or a flange. In all cases 100 percent of the weld material will be examined. In instances where ultrasonic examinations cannot be performed on 100 percent of the volume of the weld and heat affect-ed zone, surface examinations will be performed to supplement the limited volumetric axamination.
In ir.,tances where the locations of pipe supports or hangers restrict the ac-ce
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N.- %.J FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS
- TABLE CODE -
TABLE IWB-2500 APPLICABLE SECTION XI IWB-2600 EXAMINATION SYSTEM OR TO -
METHOD OF CODE RELIEF ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED EXAMIN ATION REQUESTED Bl.1 B-A Reactor Vessel III-A Upper-to-Intermediate Shell Volumetric flo Course Circumferential Weld Bl.1 B-A Intermediate-to-Lower Shell Volumetric No Course Circunferential Weld Bl.1 B-A Intermediate Shell Course Volumetric o Longitudinal Welds (2)
Bl.1 B-A Lower Shell Course Longi- Volumetric No tudinal Welds (2)
Bl.2 B-B Lower Head-to-Shell Circum- Volumetric No ferential Weld ,,
Bl.2 B-8 Lower Head Ring-to-Disc Volumetric No Circumferential Weld Bl.3 B-C Flange-to-Vessel Weld Volumetric No Bl.3 B-C Closure Head-to-Flange Weld Volumetric No .
Bl.4 B-D Outlet Nozzle-to-Shell Volumetric No Welds (3) and nozzle inside radiused sections (3)
Bl.4 B-D In'.et Nozzle-to-Shell Welds Volumetric flo (3) and nozzle inside radiused sections (3)
- This applies to components identified as AftS Safety Class 1. e.ss o
FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS
- TABLE CODE TABLE IWB-2500 APPLICABLE SECTION XI IWB-2600 EX AMIN ATION ' SYSTEM OR TO METHOD OF CODE RELIEF ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED EXAMINATION REQUESTED Bl.5 B-E Reactor Vessel III-A CRDM, Vent and In-Core Visual No (Continued) instrumentation penetra-tions and CRDM seal welds Bl.6 B-F Primary Nozzle-to-Safe-End Volumetric & No m Uelds Surface i
Bl.7 B-G-1 Closure Studs (In Place) Not Applicable No - 2.3.1 Bl.8 B-G-1 Closure Studs and Nuts Volumetric & No (When Removed) Surface Bl.9 B-G-1 Vessel Flange Ligaments Volumetric No Bl.10 B-G-1 Closure Washers Visual No Bl.ll B-G-2 Conoseal Bolting Visual No Bl.12 B-H Integrally-Helded Supports Not Applicable No - 2.3.2 Bl.13 B-I-l Closure Head Cladding Visual & No Surface Bl.14 B-I-1 Vessel Cladding Visual No Bl.15 B-N-1 Vessel Interior Surfaces Visual No and Internals z4554
.O O O FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM -
ASME CODE CLASS 1 COMPONENTS
- TABLE CODE TABLE IWB 2500 APPLICABLE SECTION Xi IWB-2600 EXAMINATION SYSTEM OR TO METHOD OF CODE RELIEF ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED EXAMINATION REQUESTED Bl.16 B-N-2 Reactor Vessel III-A Interior Attachments and Not Applicable No - 2.3.3 (Continued) Core Support Structures Bl.17 B-N-3 Core Support Structures Visual No m B1.18 B-0 Control Rod Drive Housings Volumetric No Bl.19 B-P Exempted Components Visual No B2.1 B-B Pressurizer .III-A Circumferential Shell Welds Volumetric Yes- 2.3.11 (5) 2.3.12 B2.1 B-B Longitudinal Shell Welds (3) Volumetric Yes - 2.3.11 2.3.12 B2.2 B-D Nozzle-to-Vessel Welds (6) Volumetric Yes - 2.3.4 and nozzle-to-vessel 2.3.11 radiused sections (6) 2.3.12
-B2.3 B-E Heater Penetrations Visual No B2.4 B-F Nozzle-to-Safe-End Welds Surface and No (6) Volumetric B2.5 B-G-1 Pressure-Retaining Bolting Not Applicable No (In Place)
- B2.6 8-G-1 Pressure-Retaining Bolting Not Applicable No (When Removed)
B2.7 B-G-1 Pressure-Retaining Bolting Not Applicable No
9 m FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS
- TABLE CODE TABLE IWB-2500 APPLICABLE SECTION XI IWB 2600 EXAMINATION SYSTEM OR TO METHOD OF CODE RELIEF ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED EXAMIN ATION REQUESTED B2.8 B-H Pressurizer III-A. Integrally-Welded Support Volumetric No (Continued) 82.9 B-I-2 Vessel Cladding Visual No m B2.10 B-P Exempted Components Visual No I:n B2.11 B-G-2 Manway Bolting Visual No B3.1 B-B Steam Genera- III-A Channel-Head-to Tubesheet Volumetric Yes- 2.3.11 tors (3) Weld (3) 2.3.12-(Primary Side)
B3.2 B-D Nozzle-to-Vessel Welds, and Not Applicable No nozzle inside radiused sections B3.3 B-F Nozzle-to-Safe End Welds Volumetric & Yes - 2.3.5 (6) Surface B3.4 B-G-1 Pressure-Retaining Bolting Not Applicable No (In Place)
B3.5 B-G-1 Pressure-Retaining Bolting Not Applicable No (When Removed)
B3.6 B-G-1 Pressure-Retaining Bolting Not Applicable Na B3.7 B-H Integrally-Welded Supports Not Applicable No B3.8 B-I-2 Vessel Cladding Visual No 2455-0 L
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FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS
(Primary Side)
B3.10 B-G-2 Manway Bolting Visual No
$ B4.1 B-F Piping Pres- III-l Safe-End-to-Pipe Welds Volumetric Yes - 2.3.5 sure Boundary and Surface B4.2 B-G-1 Pressure-Retaining Bolting Not Applicable No (In Place) 84.3 B-G-1 Pressure-Retaining Bolting Not Applicable No (When Removed)
B4.4 B-G-1 Pressure-Retaining Bolting Not Applicable No B4.5 B-J Circumferential and Longi- Volumetric Yes - 2.3.6 tudinal Pipe Welds B4.6 B-J Branch Pipe Connection Welds Volumetric Yes - 2.3.7 exceeding 6-inch diameter G4.7 B-J Branch Pipe Connection Welds Surface No 6-inch diameter and smaller 84.8 B-J Socket Welds Surface No B4.9 B-K-1 Integrally-Welded Supports Volumetric Yes - 2.3.8 24550
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FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS
- TABLE CODE TABLE IWB-2500 APPLICABLE SECTION XI IWB-2600 EXAMINATION SYSTEM OR TO METHOD OF CODE RELIEF ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED EXAMIN ATION REQUESTED B4.10 B-K-2 Piping Pres- -III-1 Support Components Visual No sure Boundary B4.11 B-P Exempted Components Visual No B4.12 B-G-2 Pressure-Retaining Bolting Visual No B5.1 B-G-1 Reactor Cool- P&V 1 Pressure-Retaining Bolting Volumetric Yes - 2.3.9 ant Pump (In Place)
B5.2 B-G-1 Pressure-Retaininc Jolting Volumetric Yes - 2.3.10 (When Removed) and Surface B5.3 B-G-1 Pressure-Retaining Bolting Visual No B5.4 B-K-1 Integrally-Welded Supports Not Applicable No i
l RG. 5 B-K-2 Support Components Visual No B5.6 B-L-1 Pump Cas'1g Welds Not Applicable No B5.7 B-L-2 Pump Casing Visual No B5.8 B-P Exempted Components Visual No B5.9 B-G-2 Pressure-Retaining Bolting Not Applicable No B6.1 B-G-1 Valve Pressure P&V1 & III-A Pressure-Retaining Bolting Not Applicable No Boundary (In Place) 24 $5 -0 u___ _ _ _ _ _ _ _ _ _ ___ __
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FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 1 COMPONENTS
B6.3 B-G-1 Pressure-Retaining Bolting Not Applicable No B6.4 B-K-1 Integrally-Welded Supports Not Applicable No 7
- B6.5 B- K-2 Support Components Visual No B6.6 B-M-1 Valve Body Welds Not Applicable No B6.7 B-M-2 Valve Bodies Visual No B6.8 B-P Exempted Components Visual No B6.9 B-G-2 Pressure-Retaining Bolting Visual No l
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.- 2.3 Requests for' Relief from ASME Section XI Requirements
- ' 2.3.1 RELIEF REQUEST i
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L - COMPONENT: Reactor Vessel CODE CLASS: 1 EXAMINATION REQUIREMENT:
1-Table IWB-2600 Item B1.7 requires volumetric examination of closure studs while
- in place in'the vessel flange.
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i BASIS FOR RELIEF:
j The reactor vessel closure studs are removed during each refueling and there i will be no need for examination in place as required by IWB-2600.
ALTERNATIVE EXAMINATION: .
! Volumetric and surface examinations will be performed when studs are removed.
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- COMPONENT: Reactor Vessel CODE CLASS: 1 l EXAMINATION REQUIREMENT:
i- Table IWB-2600 Item 81.12 requires volumetric examination of integrally-welded supports.
BASIS FOR RELIEF:
- The reactor vessel is supported by pads integral with the primary nozzles and 4 are excluded.from the volumetric examination requirements of IWB-2500 Category B-H.
ALTERNATIVE' EXAMINATION: ;
i Nozzle-to-vessel welds.are volumetrically examined at extent and frequency re- ;
i quired by IWB-2500 Category B-D.
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!~~ 2.313 RELIEF REQUEST COMPONENT: Reactor Vessel CODE CLASS: 1 i
- EXAMINATION REQUIREMENT
- Table IWB-2600 Item Bl.16 requires visual' examination of the vessel interior i attachmaats and core support structures.
L BASIS FOR RELIEF:
As identified by-IWB-2500 Category B-N-2, this requirement of IWB-2600 is ap-plicalle only to Boiling Water type reactors.
ALTERNATIVE EXAMINATION:
Examinations will be performed E- required by IWB-2600 Items Bl.15 and Bl.17.
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NOZZLE-TO-VESSEL WELD
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WELD DEPOSITED CLADING ;
(STAIN LESS STEEL WELD) I 1
6 PRESSURIZER NOZZLE - TO - VESSEL WELD CONFIGURATION Figure - B2.2 2534-0
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.i 2.3.4 RELIEF REQUEST
-COMPONENT: Pressurizer CODE CLASS: 1 1
EXAMINATION REQUIREMENT,1 Tables IWB-2500 Category B-D and IWB-2600 Item B2.2 require volumetric examina-tion of the nozzle-to-vessel welds and adjacent base metal for one wall thick-ness on either side of the weld.
BASIS FOR RELIEF:
The geometric configuration of the nozzle prevents ultrasonic examinations from being performed from the nozzle side of the weld to the extent required i by IWB-2600. Examination will be performed from both the weld and shell sur-faces. The nozzle configuration is shown in Figure 82.2.
J ALTERNATIVE EXAMINATION:
One bundred percent of the weld, the heat affected zone, and the required amount t
of base metal on the shell side of the weld will be examined. Base metal on the' nozzle side of the weld will be examined to the extent practical, which is approximately-25 percent.
In addition,-the welds will receive surface examination on those areas not scanned by UT.
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2.3.5 RELIEF REQUEST COMPONENT: Steam Generators (3) CODE CLASS: 1 EXAMINATION REQUIREMENT:
Tables IWB-2500 Category B-F and IWB-2600 Item B3.3 require surface and volu-metric examinations of the nozzle-to-safe-end welds and the adjacent base metal for one wall thickness on either side of the welds.
BASIS FOR RELIEF:
Examination of the steam generator primary nozzle safe-end-to pipe welds is limited by the nozzle geometry and surface condition, and by the limited sur-face preparation on the pipe side of the weld. The surface on the pipe side of the weld, which is a cast elbow, is machined for a distance of apprcximately 5 1/4 inches from the edge of the weld. Ultrasonic examination is limited to this distance from the edge of the weld. Examinations can be performed on the surf ace of the weld but are severly limited from the nozzle side by the con-figuration of weld build up and weld overlay. Weld configuration is shown in
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fL.)x ALTERNATIVE EXAMINATION:
Ultrasonic examinations will be performed from both the pipe and weld surfaces as allowed by T-532 of Section V. All of the weld metal, including the weld root, will be inspected. Since no UT can be performed on the nozzle side of the weld, the extent of examination is limited to approximately 90 percent of the code-required area. Surface examinations will be performed on essentially 100 percent of the required area.
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T S.G. NOZZLE INTEGRALLY CAST WITH HEAD (CAST CARBON STEEL) .
FERRITIC WELD BUILD UP WELD OVERLAY (INCONEL)
" BUTTERED" SAFE END (5TAINLESS STEEL WELD) u,_ REACTOR ,
COOLANT PIPE
,_ 5.25 INCHES .!
(CAST AUSTENITIC i
N' I L STAIN LESS STEE L)
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WELD DEPOSITED CLADDING (STAINLESS STEE L WE LD)
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PlPE-TO-SAFE END WELD (STAIN LESS STEEL WELD) k STEAM GENERATOR PRIMARY NOZZLE SAFE - END TO PIPE WELD CONFIGURATION Figure - B3.3 3
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d 2.3.6 RELIEF REQUEST COMPONENT: Piping Pressure Boundary CODE CLASS: 1 EXAMINATION REQUIREMENT:
Tablea IWB-2500 Category B-J and IWB-2600 Item 84.5 require volumetric examina-tion of circumferential butt welds plus the ' adjacent base material for a dis--
tance of one wall-thickness on either side of the weld.
BASIS FOR RELIEF:
l; Instan:es occur where pipe welds are between fittings, such as elbow-to-valve or flange-to-elbow welds. In such instances access may be severely limited and ultrasonic- examination cannot be performed on 100 percent of the volume of the weld and the heat affected zone.
ALTERNATIVE EXAMINATION:
Ultrasonic examinations will be performed to the extent practical and will f"*g be supplemented by surface examination.
C Welds which'will require supplemental surface examination, along with the esti-mated extent of volumetric examination, are as follows:
APR-1-4105, Loop l'RTD return, weld #16 --40%
APR-1-4109, Loop 1 Cold Leg SIS, weld #8 - 60%
APR-1-4208, Pressurizer Spray, weld #42 - 70% ,
weld #43 70% i APR-1-4307, Loop 3 RTD Return, weld #8 - 60%
APR-1-4501,. Pressurizer Relief, weld #14 - 50%
APR-1-4502, Pressurizer Safety, weld #2 - 70%
weld #5 - 80%
weld #12 - 70%
weld #16 - 80%
weld #20 - 80%
weld #24 - 70%
weld #27 - 80%
Pressurizer Safety (APR-1-4502) welds #29, 31, and 32 are inaccessible.
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- V 2.3.7 RELIEF REQUEST COMPONENT: Piping Pressure Boundary CODE CLASS: 1 EXAMINATION REQUIREMENT:
1 Tables IWB-2500 Category B-J 'and IWB-2600 Item B4.6 require volumetric examina-tion of branch pipe connection welds of branch connections exceeding 6-inch diameter.
2 BASIS FOR RELIEF:
The geometric configuration of the welds as shown in Figure B4.6 prevents ultrasonic examinations from being perfonaed from the weld surfaces. ,
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ALTERNATIVE EXAMINATION:
Volumetric examinations will-be performed to the extent practical from the pipe and nozzle surfaces aojacent to the weld. Surface examination of the welds will be performed to supplement the volumetric examination.
The welds to which this relief request applies, along with the estimated ex- 1 tent of volumetric examination, are as follows: 1 I
Reactor Coolant Loop #1, weld #16BC - 80%
Reactor Coolant Loop #1, weld #22BC - 80% l Reactor Coolant Loop #2, weld #16BC - 80% i Reactor Coolant Loop #2, weld #21BC.- 80% i Reactor Coolant Loop #2, weld #16BC - 80%
. Reactor Coolant Loop #3, weld #21BC - 80%
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REACTOR COOLANT PIPE (CAST AUS TENITIC STAINLES.i STEEL) 3 BRANCH NOZZLE CONNECTION WELD Figure - B4.6 2534-0 E-19
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2.3.8. RELIEF REQUEST COMPONENT: Integrally-Welded Supports CGDE CLASS: 1 EXAMINATION REQUIREMENT:
Tables IWB-2500 Category B-K-1 ar.d IWB-2600 Item B4.9 require volumetric exam-
.ination of the weld, the base metal beneath the weld and base metal along the support attachment member for integrally-welded supports.
BASIS FOR RELIEF:
The piping systems' integrally-welded supports are attached to the pipes by fillet welds. The configurations of these welds are such that examinations cannot be performed to the extent required by IWB-2600. Only the base material of the pipe wall and the base metal of the support attachment can be volume--
trically examined.
ALTERNATIVE EXAMINATION:
. Surface examination will be performed on the integrally-welded attachments to
! ,<( g) supplement the volumetric examination.
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.D,s 2.3.9 RELIEF REQUEST COMPONENT: Reactor Coolant Pump CODE CLASS: 1 t
i EXAMINATION REQUIREMENT:
Table IWB-2600 Item B5.1 requires volumetric examination of the seal housing bolting while in place.
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-BASIS FOR RELIEF:
The reactor coolant pump' seal housing' bolts are of the socket-head type and the configuration is such that ultrasonic examination as required by IWB-2600 cannot be performed when the bolting is-in place.
. ALTERNATIVE EXAMINATION:
Volumetric and surface examinations will be performed as required by IWB-2600 Item B5.3 if the seal housing is disassembled for maintenance. If no disas-sembly for maintenance is required within the 120-month inspection interval, then disassembly will be performed for inspection.
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- i. 2.3.10 RELIEF REQUEST i
)- COMPONENT: Reactor' Coolant Pump- CODE CLASS: 1
, EXAMINATION REQUIREMENT:
l Table'IWB-2600 Item B5.2 requires volumetric and surface examinations of the
. ' pump main-flange closure bolts 'when removed.
I
- - BASIS FOR RELIEF
Removal of the bolts for examination would require detensioning the bolts and violation' of the pump pressure boundary integrity.
ALTERNATIVE EXAMINATION:
- - The reactor coolant pump main-flange bolting is ultrasonically examined in
C' - when a pump will be disassembled for the performance of the volumetric examina-tion required by Category B-L-1.
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2.3.11 RELIEF REQUEST COMPONENT: Pressurizer and Primary Portions of the CODE CLASS: 1 Steam Generators.
EXAMINATION REQUIREMENT:
Requirement #1: The 1974 Edition of Section XI, I-3121 states, " Material from which the block is fabricated shall be from the component, from either a noz-zle dropout or a prolongation."
Requirement #2: The Summer 1975 Addenda of Section XI, I-3121 states,
" Material from which the block is fabricated shall be from one of the following:
(1) the component nozzle dropout; (2) the component prolongation; or (3) when it is not possible to fabricate the block from material taken from the compon-ent, it may be fabricated from a material of a specification included in the applicable examination volumes of the component. The acoustic velocity and attenuation of such a block shall be demonstrated to fall within the range of straight beam longitudinal wave velocity and attenuation found in the unclad component."
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(nj ! BASIS FOR RELIEF:
Requirement #1 cannot be met. At the time the components were built, no excess material was saved for fabrication of calibration blocks. ,
Requirement #2 cannot be met because the Code assumes an " unclad component", ;
when in fact all the components are clad on the inner surfaces. j l
ALTERNATIVE EXAMINATION:
Calibration blocks required for the examination of welds in these vessels will be fabricated from material of the same specification, product form, and heat treatment as one of the materials being joined as allowed by Article T-434.1.1 in the Winter 1976 Addenda of Section V of the ASME Boiler and Pressure Vessel Code which states, "The material from which the block is fabricated shall be from one of the following: (1) nozzle drop out from the component; (2) a component prolongation; or (3) material of the same material specification, product form, and heat treatment ~as one of the materials being joined."
O gj 2-23
4
.O 2.3.12 RELIEF REQUEST COMPONENT: Pressurizer and Primary Portions of the CODE CLASS: 1 Steam Generators.
EXAMINATION REQUIREMENT:
I-3122 requires that if the component is clad, then the calibration block shall be clad.
BASIS FOR RELIEF:
The calibration blocks for the manual ultrasonic examination of the referenced components are not clad. However, the lack of cladding does not affect the calibration of the ultrasonic equipment. Onlv the top (0.D.) portions of the blocks are actually used in the calibrations. Specifically, three side-drilled haies, at depths of 1/4 T, 1/2 T, and 3/4 T, are utilized.
The I.D. of the blocks do contain a 2% T notch. However, it is only used for reference. The amplitude response from the notch is not required to be above a certain minimum. In~ fact, the am91itude is not even recorded. Cladding the
}
,j blocks could cause the amplitude response to either increase or decrease. In
, either case, the calibration would not be affected.
ALTERNATIVE EXAMINATION:
The existing unclad calibration blocks, required for the examination of welds 4 in these vessels will be utilized for the calibration of ultrasonic equipment.
1 1
v 2-24 4
4'
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3.0 - INSERVICE INSPECTION OF CLASS 2 COMPONENTS
.A V
The following table ~provides a listing of the Class 2 pressure-retainiPO com-ponents (and their-supports) which are subject to the inspection requirements of Subsection IWC of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summer, 1975.
This tabulation identifies the components to be inspected, the component's safety class, the applicable code to which the component was built, and the method of examination. Relief from the inspection requirements of Subsection IWC is requested in cases where these inspection requirements have been deter-mined to be impractical. Where relief is requested specific information is provided which identifies the applicable code requirements, justification for the relief request, and the inspection method to be used as an alternative.
As indicated in the tabulation, some components included in this program were not built to the ASME Section III Code because it was not in effect at the time the component was purchased. However, these components will be
- inspected in accordance with the requirements of Subsection IWC to the extent i practical.
The abbreviations used within this table for " Codes Applicable to Construction" are defined as follows:
i III-A = ASME Boiler and Pressure Vessel Code-Section III, Class A
( III-C = ASME Boiler and Pressure Vessel Code-Section III, Class C P&V II = ASME Code for Pumps and Valves for Nuclear Power, Class 2 l (
III-2 = ASME Boiler and Pressure Vessel Code-Section III, Class 2 y
3.1 Non-Applicable Code Requirements The tabulation of inspection requirements for the Class 2 components identify items where the examination requirements of Table IWC-2600 are not applicable.
Specific details are as follows:
3.1.1 The letdown heat exchanger inlet and outlet nozzles are 3-inch nominal diameter, the integrally-welded supports are on the shell (Class 3) side of the vessel, and tube-sheet flange bolting is 1-inch diameter.
3.1.2 The excess letdown heat exchanger inlet and outlet nozzles are 2-inch nominal diameter and the integrally-welded supports are on the shell-(Class 3) side of the vessel.
3.1.3 The regenerative heat exchanger inlet and outlet nozzles are 3-inch nominal diameter and there is no pressure-retaining bolting.
3.1.4 There are no integrally welded supports on the steam generators.
3.1.5- The volume control tank inlet and outlet nozzles are 4, 3 and 1-inch nominal diameter.
3-1
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3.1.6 The seal water return filter inlet and outlet nozzles are 2-inch nominal diameter-and pressure retaining bolting is 1/2-inch diameter.
- 3. '1. 7 The seal water heat exchanger inlet and outlet nozzles are 4-inch nominal diameter, the integrally-welded supports are located on the shell (Class 3) side of the vessel and tubesheet flange bolting is 3/4-inch diameter.
3.1.8 The reactor coolant filter inlet and outlet nozzles are 2-inch nominal diameter and cover bolting is 1/2-inch diameter. '
3.1.9 There are no pressure-containing welds in the residual heat removal pump casings.
3.1.10 There are no Class 2 valves with pressure-containing welds or inte-grally-welded supports.
3.1.11 The seal water injection filter is manufactured from 4-inch nominal diameter pipe.
< 3.1.12 The letdown delay tank inlet and outlet nozzles are 3-inch nominal diameter and there is no pressure-retaining bolting.
j 3.1.13 The excess letdown delay tank inlet and outlet nozzles are 1-inch nominal diameter and there is no pressure-retaining bolting.
/"~%
'Q 3.2 EXEMPT COMPONENTS 3.2.1 All Class 2 piping with a nominal diameter of 4 inches or less is excluded from the examination requirements of IWC-2520 by the application of the criteria given in IWC-1220(d).
3.2.2 The following components are exe.npt from the examination requirements of IWC-2520 by application of the criteria given in IWC-1220. These components will be examined in accordance with the requirements of IWC-2510.
3.2.2.1 CVCS Seal Water Injection Filters (2). These components are exempt under IWC-1220(d).
3.2.2.-2 Safety Injection Accumulators (3). These componeits are exempt under IWC-1220(c).
3.2.2.3 Boron Injection Tank. This component is exempt under IWC-1220(c).
3.2.2.4 Containment Spray Pumps (2). These components are exempt under IWC-1220(b).
. v( h 3-2
s 3.2.2.5 The' Refueling Water Storage Tank (RWST) and (a) suction piping from
,^[ ) the RWST to the HHSI pumps, (b) suction piping from the RWST to the
\~ ' LHSI/RHR pumps, (c) suction piping from the RWST to the CTMT spray pumps. These components are exempt under IWC-1220(a).
3.3 ,
Hydrostatic Testing 3.3.1 Subsections IWB and IWC contain differing requirements for the hydrostatic testing of Class 1 and Class 2 systems and components. The implementation of these requirements is impractical when the only means of pressurizing the Class
- 2 system is through the Class 1 system or when the boundary between the two systems is a check valve arranged for flow from the Clasr " .c the Class 1 system. Exception is taken to the performance of the hydro,.atic test require-ments as required by Article IWC-2412 (a) on those portions of the Class 2 systems identified below. Visual examination for evidence of leakage will be conducted on these portions of the systems at the system nominal operating pressure in accordance with the requirements of IWB-5221 for the adjoining Class 1 system.
Each of the listed portions of Class 2 systems has a design pressure of 2485 psig. The operating pressure of the reactor coolant system is 2235 psig. To meet the requirements of IWC-2412 (a) each line would have to be tested at a pressure of 1.05 X 2485 at 500 F, i.e., 2609 psig. To meet the requirements of IWB-5221 the lines would require testing at 1.02 X 2235 at 500*F, i.e.,
f- s 2280 psig. The 15 portions of systems involved either cannot be isolated from
()-
the Class 1 systems or can only be pressurized through the Class 1 systems.
3.3.1.1 R. C. pump seal bypass lines from the orifices to A0 valve CV 8142.
3.3.1.2 R. C. pump seal leak of f lines to air-operated valves 8141 A, B and C.
3.3.1.3 R. C. pump seal injection lines from check valves 8367 A, B and C to manually-operated valves 8350 A, B and C.
3.3.1.4 Excess letdown from valve CV 8153 to HCV 137.
3.3.1.5 Letdown line from valve LCV 459 to orifice outlet valves 8149 A, B and C.
3.3.1.6 PZR steam space sampling line to valve 8078, PZR liquid space sampling line to valve 8080 and loop sampling lines to valves 8056 and 8077.
3.3.1.7 Charging line from check valve 8347 to air-operated valve CV8146 and bypass line to manually-operated valve 8392.
3.3.1.8 Alternate charging line from check valve 8346 to air-operated valve CV 8147.
3.3.1.9 Reactor Coolant Loop flowmeter elbow taps.
3-3
3.3.1.10 Pressurizer level control instrumentation lines.
1 1 v 3.3.1.11 Reactor coolant.RTD system vent and drain lines.
3.3.1.12;R.C. pump seal injection and seal by pass vent and drain lines.
3.3.1.13 Pressurizer spray control valve by pass lines.
3.3.1.14 Pressurizer safety valve water seal drain lines to valve 8064.
3.3.1.15 RHR take-off line connections to pressure transmitters PT 402 and 403.
3.3.2 The implementation of the pressure test requirements of Subsection IWC is con-
- sidered impractical when a section of Class 2 piping cannot be pressurized without overpressurizing connecting piping of a lower pressure class. Excep-3 tion is taken to the performance of the hydrostatic test requirements of Article IWC-2412 on portions of Class 2 systems as follows: '
3.1.2.1 Charging pump discharge lines between the charging pumps and isola-tion valves Q2E21V123 A, B, C; and mini-flow piping to isolation valve Q2E21V265.
- Visual examination for evidence of leakage will be conducted on these p lines while at nominal operating pressure.
3.3.2.2 Volume control tank spray line from valve Q2E21V152 to the volume l control tank; Chemical ' injection to main feedwater lines between valves Q2N25V002 A, B,-C and the main feedwater lines;
- Main feedwater lines from valves Q2N21V001 A, B, and C to the steam generators; Steam generator blowdown lines to valves Q2E24V003 A, B, C; Auxiliary feedwater piping from valves Q2N23V011 A, B, and C to the main feedwater lines; Gross failed fuel detector to letdown between Q2E21V400 and the con-nection with Q2E21GCB '.
Visual examination for evidence of leakage will be conducted on these lines according to the requirements of IWC-2412 for the connecting piping of the-lower pressure class.
3.3.2.3 Relief line discharge header to pressurizer relief tank. This line
, cannot be. isolated from the pressurizer relief tank.
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FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS
C1.1 C-A Shell-to-Flange Weld Volumetric No Y C1.2 C-B Nozzle-to-Vessel Weld Not Applicable No C1.3 C-C- Integrally-Welded Supports Not Applicable No Cl.4 C-D Tubesheet Flange Bolting Not Applicable No C1.1 C-A Excess Letdown III-C Head-to-Flange Weld Volumetric Yes - 3.4.8 Heat Exchanger (Tube Side)
C1.2 C-B Nozzle-to-Vessel Weld Not Applicable No Cl.3 C-C Integrally-Welded Supports Not Applicable No Cl.4 C-D Tubesheet Flange Bolting Visual and No Volumetric Cl.1 C-A Regenerative III-C Head-to-Shell Welds (6) Volumetric Yes - 3.4.1 Heat Exchanger 3,4.10 Cl.1 C-A Shell-to-Tubesheet Welds Volumetric Yes - 3.4.1 (6) 3.4.10
- This applies '.o components identified as ANS Safety Class Ea. ms-o
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FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS
Cl.3 C-C Integrally-Welded Supports Surface No
[ C1.4 C-D Pressure-Retaining Bolting Not Applicable No i
Cl.1 C-A Residual Heat -III-C Head-to-Shell Welds (2) Volumetric No Exchangers (2)
(Tube Side)
Cl .-l C-A Shell-to-Tubesheet Welds Volumetric No (2)
C1.2 C-B Nozzle-to-Vessel Welds Not Accessible Yes - 3.4.2 C1. 3 C-C Integrally-Welded Supports Not Applicable No Cl.4 C-D Tubesheet Flange Bolting Visual and No (96) Volumetric C1.1 C-A Seal Water III-C Cover-Weldment-to-Shell Volumetric Yes - 3.4.3 Return Filter Weld C1.1 C-A Head-to-Shell Weld Volumetric Yes - 3.4.3 C1.2 C-B Nozzle-to-Vessel Weld Not Applicabic No 44 b5-0
- - - - ~ . .. . - - _ . - .- _ . . .. . ,
FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS
- TABLE CODE !
TABLE '
IWC-2520 APPLICABLE SECTION XI IWC-2600 EXAMINATION SYSTEM OR TO METHOD OF CODE RELIEF-ITEM NO. CATEGORY COMPONENT CONSTRUCTION - AREA TO BE EXAMINED EX AMIN ATION REQUESTED C1.3 C-C Seal Water III-C Integrally-Welded Supports Surface No Return Filter (Continued)
C1.4 C-D Pressure-Retaining Bolting Not Applicable No C1.1 C-A Volume Control III-C Upper-Head-to-Shell Weld Volumetric No Tank '
Cl.1 C-A Lower-Head-to-Shell Weld Volumetric No Cl.2 C- B Nozzle-to-Vessel Weld Not Applicable No Cl.3 C-C Integrally-Welded Supports Surface No Cl.4 C-D Manway Bolting Visual and No Volumetric Cl.1 C-A Letdown Reheat III-C Head-to-Shell Weld Volumetric Yes - 3.4.3 i Heat Exchanger 3.4.9 (Tube Side)
Cl.1 C-A Shell-to-Flange Weld Volumetric Yes - 3.4.3 3.4.9
- C1.2 C-B Nozzle-to-Vessel Weld Not Applicable No Cl.3 C-C Integrally-Welded Supports Surface No 1
a
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Q V J FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS
- TABLE CODE TABLF [ IWC-2520 APPLICABLE SECTION XI IWC-26001 EXAMINATION SYSTEM OR* TO METHOD OF CODE RELIEF ITEM NO. CATEGORY COMPONENT CONSTR,UCTION AREA TO BE EXAMINED EXAMIN ATION REQUESTED C1.4 C-D Letdown Reheat III-C Pressure-Retaining Bolting Not Applicable No Heat Exchanger (Tube Side)
C1.1 C-A Seal Water III-C Head-to-Shell Weld Volumetric Yes - 3.4.3 Heat Exchanger
'[ (Tube Side)
Cl.1 C-A Shell-to-Flange Weld Volumetric Yes - 3.4.3 Cl.2 C-B Nozzle-to-Vessel Welds Not Applicable No Cl . 3 C-C Integrally-Welded Supports Not Applicable No Cl.4 'C-D Tubesheet Flange Bolting Not Applicable No Cl.1 C-A Steam Genera- III-A Upper-Head-to-Shell Weld Volumetric Yes - 3.4.11 tors (3)
(Shell Side)
Cl.1 C-A Upper-Shell-to-Transition Volumetric Yes - 3.4.11 Weld C1.1 C-A Transition-to-Lower-Shell Volumetric Yes - 3.4.11 Weld Cl.1 C-A Lower-Shell-to-Stub-Barrel Volumetric Yes - 3.4.11 Weld t4M O
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N FARLEY NUCLEAR PLANT UNIT NO.2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS
Cl.2 C-3 Steam-Outlet-Nozzle-to-Shell Volumetric Yes - 3.4.11 w Weld C1. 2 C-B Feedwater-Inlet-Nozzle-to- Volumetric Yes - 3.4.11 Shell Weld C1. 3 C-C Integrally-Welded Supports Not Applicable No Cl.4 C-D Manway Bolting Visual and No Volumetric Cl.1 C-A Reactor Cool- III-C Cover-Weldment-to-Shell Volumetric Yes - 3.4.3 ant Filter Weld -
C1.1 C-A Head-to-Shell Weld ,
Volumetric Yes - 3.4.3
~
Cl.2 C-B Nozzle-to-Vessel Weld Not Apolicable No. l C1.3 C-C Integrally-Welded Suports Surface No Cl . 4 C-D Pressure-Retaining Bolting Not Applicabic No
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V FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS
Cl.2 C-B Nozzle-to-Vessel Welds Not Applicable No w C1.3 C-C Integrally-Welded Supports Surface No
'Cl.4 C- D Pressure-Retaining Bolting Not Applicable No Cl.1 C-A Excess Letdown III-2 Delay Tanks (2)
Heat-to-Shell Welds (4) Volumetric No Cl.2 C-B Nozzle-to-Vessel Welds Not Applicable No Cl.3 C-C Integrally-Welded Supports Surface No Cl.4 C-D Pressure-Retaining Bolting Not Applicable No C2.1 C-F; C-G Piping Systems III-2 Circumferential Butt Welds Volumetric Yes - 3.4.4 C2.2 C-F; C-G Longitudiml Weld Joints in Volumetric No Fittings C2.3 C-F; C-G Branch-Pipe-to-Pipe Welds Volumetric Yes - 3.4.6 C2.4 C-D Pressure-Retaining Bolting Visual and No Volumetric
/4 *a5 0
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FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM AST IE CODE CLASS 2 COMPONENTS
- TABLE CODE TABLE IWC-2520 ' APPLICABLE SECTION XI IWC-2600 EXAMINATION SYSTEM OR TO METHOD OF CODE RELIEF ITEM NO. CATEGORY COMPONENT CONSTRUCTION AREA TO BE EXAMINED EXAMINATION REGUESTED C2.5 C-E-1 Piping Systems III-2 Integrally-Welded Supports Surface No C2.6 C-E-2 Support Components Visual No C3.1 C-F Residual Heat P&V II Pump Casing Welds Not Applicable No Removal Pumps y
m (2)
C3.2 C-D Pressure-Retaining Bolting Visual and No Volumetric C3.3 C-E-1 Integrally-Welded Supports Not Applicable No C3.4 C-E-2 Support Components Visual No C3.1 C-F Centrifugal P&V II Pump Casing Welds Volumetric Yes - 3.4.5 Charging Pumps (3)
C3.2 C-D Pressure-Retaining Bolting Visual and No Volumetric l
C3.3 C-E-1 Integrally-Welded Supports Surface Yes - 3.4.7 C3.4 C-E-2 Support-Components Visual No C4.1 C-F, C-G Valves talve Body Welds Not Applicabic No C4.2 C-D ' Pressure-Retaining Bolting Visual and No Volumetric e.sso
cy O O FARLEY NUCLEAR PLANT UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 2 COMPONENTS
i I
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3.4 Requests for Relief from ASME Section XI Requirements 3.4.1 RELIEF REQEST COMPONENT: Regenerative Heat Exchanger CODE CLASS: 2 EXAMINATION REQUIREMENT:
Tables IWC-2520 Category C-A and IWC-2600 Item C1.1 require volumetric examina-tion of the heat exchanger head-to-shell and-shell-to-tubesheet welds.
BASIS FOR RELIEF:
The regenerative heat exchanger shell is fabricated from centrifugally cast austenitic steel material which limits ultrasonic examination as required by IWC-2600 to the half-node technique. The geometric configuration of the weld surface and the location of adjacent nozzles and supports provide limitations to the extent of the examinations coverage.
ALTERNATIVE EXAMINATION:
Surface examinations will be performed to supplement the volumetric examina-tions.
I h
3-13
'%./
3.4.2 RELIEF REQUEST COMPONENT: Residual Heat Removal (RHR) CODE CLASS: 2 Heat Exchangers (2)
EXAMINATION REQUIREMENT:
Tables IWC-2520, Category C-B and IWC-2600, Item C1.2 require volumetric exam-ination of the nozzle-to-vessel welds.
BASIS FOR RELIEF:
The RHR Heat Exchanger nozzle-to-vessel welds are covered by reinforcement rings and are not accessible for examination. The configuration is shown in Figure C).2.
ALTERNATIVE EXAMINATION:
The nozzles will be subject to visual inspection for evidence of leakage.
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CHANNEL HEAD FLANGE i
NOZZLE TO VESSEL WELD - .7E" THICK BY 3" WIDE
'~
REINFORCEMENT PAD i
O i
y NOZZLE (TYPICAL OF TWO)
.75" THICK SHELL AND HEAD Note: All materials and welds are stainless steel, t
RESIDUAL HEAT REMOVAL HEAT EXCHANGER NOZZLE TO l VESSEL CONFIGURATION l Figure - C1.2 l
< 1 2534-0 3-15
r V,r 3.4.3 RELIEF REQUEST COMPONENT: Seal Water Heat Exchanger CODE CLASS: 2
', Letdown Reheat Heat Exchanger Reactor Coolant Filter Seal Water Return Filter EXAMINATION REQUIREMENT:
Tables IWC-2520 Category C-A and IWC-2600 Item C1.1 require that five percent of the total length of the vessel head-to-shell and flange-to-shell welds be volumetrically examined during the ten year inspection interval.
f BASIS FOR RELIEF:
The thickness of the materials utilized for the construction of these compon-ents (0.165 to 0.188 inches) is such that meaningful results could not be l, expected with ultrasonic examination.
ALTERNATIVE EXAMINATION:
These welds will be examined by surface and visual methods.
l l
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NY 3.4.4 RELIEF REQUEST COMPONENT: Piping Pressure Boundary CODE CLASS: 2 EXAMINATION REQUIREMENTL Tables IWC-2520 Category C-G and IWC-2600 Item 2.1 require volumetric examina-tion of circe.mferential butt welds plus the adjacent base material for a dis-tance of one wall thickness on either side of the weld. ,
BASIS FOR RELIEF:
The arrangement and details of the Class 2 piping system and components were designed and fabricated before the examination requirements-of Section XI of the Code were formalized and some examinations are limited or not practical due to geometric configuration or accessibility. Generally these limitations exist at all fitting-to-fitting welds such as elbow-to-tee, elbow-to-valve, reducer-to-valve, etc. , where geometry and, sometimes, surface conditions preclude ultra-sonic coupling or access for the required scan length.
-~
x,j ALTERNATIVE EXAMINATION:
Ultrasonic examinations will be performed to the extent practical from the pipe and weld surfaces and be supplemented by surface examinations on those welds where 100 percent of the weld and heat affected zone have not been volumetrically examined. Welds requiring supplemental examination, along with the estimated extent of volumetric examination, are as follows:
ARP-2-2314, Weld #31 - 50%
Weld #32 - 50%
APR-2-2315, Weld #14 - 90%
APR-2-2316, Weld #11 - 30%
Weld #20 - 30% -
APR-2-2317, Weld #18 - 50%
s_J 3-17
A
, -d 3.4.5 RELIEF REQUEST COMPONENT: Charging Pumps (3) CODE CLASS: 2 i
't EXAMINATION REQUIREMENT:
Table IWC-2600 Item C3.1 requires volumetric examination of pump casing pres-sure-containing welds.
BASIS FOR RELIEF:
The pressure-retaining welds in the charging pump casings are not normally accessible for examination as required by IWC-2600. Examination of the charg-ing pump casing weld, Item C3.1, by ultrasonic, radiographic or surface ex-amination requires complete disassembly of the pump casing and removal of the inboard seal housing and rotor assembly.
The configuration is shown in Figure C3.1.
N ALTERNATIVE EXAMINATION:
Ultrasonic examination will be conducted whenever a pump is disassembled for maintenance reasons. If no such occasion arises, the examination will be J performed at or near the end of the 10 year interval.
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i l l PUMP CASING WELD (CARBON STEE L) t I
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> a CENTRIFUGAL CHARGING PUMP ARRANGEMENT (INBOARD END)
Figure C3.1 v
2534-0 3-19
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3.4.6 RELIEF REQUEST COMPONENT: Piping Pressure Boundary CODE CLASS: 2 and Non-Code EXAMINATION REQUIREMENT:
Tables IWC-2520, Categories C-F and C-G, and IWC-2600, Item C2.3 require vol-umetric examination of branch connection weld joints when the branch connection exceeds 4-inch diameter.
BASIS FOR RELIEF:
The geometric configuration of the welds prevents ultrasonic examinations from being performed from the weld surfaces.
ALTERNATIVE EXAMINATION:
Volumetric examinations will be performed to the extent practical from the pipe surfaces adjacent to the welds. Surface examinations of the welds will be per-formed to supplement the limited volumetric examinations.
/~'}
'O The welds to which this releft request applies, along with the estimated extent of volumetric examination, are as follows:
APR-2-2110, Weld #4-14: 80%
Weld #4-15: 80%
APR-2-2111, Weld #1-5: 80%
l Weld #1-11: 80%
Weld #1-12: 80%
Weld #1-13: 80%
Weld #1-14: 80%
l Weld #1-15: 80%
Weld #1-16: 80%
Weld #1-17: 80%
APR-2-2120, Weld #2-5: 80%
Weld #2-11: 80%
Weld #2-12: 80%
Weld #2-13: 80%
Weld #2-14: 80%
Weld #2-15: 80%
Weld #2-16: 80%
Weld #2-17: 80%
APR-2-2130, Weld #3-5: 80%
Weld #3-11: 80%
Weld #3-12: 80%
4 7-~ i e Weld #3-13: 80%
\, / Weld #3-14: 80%
Weld #3-15: 80%
Weld #3-16: 80%
Weld #3-17: 80%
3-20
. - ~_
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% s' 3.4.7 RELIEF REQUEST COMPONENT: Charging Pumps (3) CODE CLASS: 2 EXAMINATION REQUIREMENT:
Tables IWC-2520, Category C-E-1 and IWC-2600, Item C3.3 require surface exam-ination of 100 percent of the major load bearing elements of the integrally-welded supports.
BASIS FOR RELIEF:
Due to component and support designs, approximately 20 percant of each integrally-welded support is inaccassible for examination.
ALTERNATIVE E_XAMINATION:
Tne accessible portion of each support will receive visual and surface exam-inations.
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V 3-21
O V
3.4.8 RELIEF REQUEST COMPONENT: Excess Letdown Heat Exchanger CODE-CLASS: 2 EXAMINATION REQUIREMENT: ,
-Tables IWC-2520,_ Category C-A and IWC-2600, Item C1.1 require volumetric exam-inations " uniformly distributed among three areas around the vessel circum-ference."
BASIS FOR RELIEF:
r The location of adjacent nozzles provides limitations to the extent of exam-ination coverage. Consequently, the requirement for three uniformly distri-buted areas cannot be met.
4 ALTERNATIVE EXAMINATION:
The required five percent of each circumferential weld will be volumetrically
,- inspected. Two uniformly distributed areas will be inspected instead of the required three areas.
i 4
a 4
i J
i -
3-22
4 O 3.4.9 RELIEF REQUEST 4
COMPONENT: Letdown Reheat Heat Exchanger CODE CLASS: 2 EXAMINATION REQUIREMENT:
Tables IWC-2520, Category C-A and IWC-2600, Item C1.1 require volumetric exam- -
inations " uniformly distributed among three areas around the vessel circum- !
j ference".
BASIS FOR RELIEF:
, The location of adjacent cozzles provides limitations to the extent of exam-1 ination coverage. Consequently, the requirement for three uniformly distri-
! buted areas cannot be met.
i ALTERNATIVE EXAMINATION:
Two uniformly distributed areas will be inspected instead of the required three i areas. The required 5 percent of each circumferential weld will be inspected.
~However, due to the material thickness (.188 inches) the methods of exam nation i will be surface and visual as stated in Relief Request 3.4.3.
l
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, 3-23
l O 3.4.10 RELIEF REQUEST
. COMPONENT: Regenerative Heat Exchanger CODE CLASS: 2 4
EXAMINATION REQUIREMENT:
t I
Tables IWC-2520, Category C-A and IWC-2600, Item C1.1 require volumetric exami-nations " uniformly distributed among three areas around the vessel circumfer-ence."
BASIS FOR RELIEF:
The location of nozzles and supports provides limitations to the extent of examination coverage. Consequently, the requirement for thrt ; uniformly j . distributed areas cannot be met.
- ALTERNATIVE EXAMINATION:
i The required 5 percent of each circumferential weld will be volumetrically in-spected. Only one area will be inspected instead of the required three areas.
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(s 3.4.11 RELIEF REQUEST COMPONENT: Secondary portions of the Steam CODE CLASS: 2 Generators (3)
EXAMINATION REQUIREMENT: ,
The 1974 Edition of Section XI, I-3121 states, " Material from which the block 3 is fabricated shall be from the component, from either a nozzle dropout or a prolongation."
BASIS FOR RELIEF:
At the time the components were built, no excess material was saved for the fabrication of calibration blocks.
ALTERNATIVE EXAMINATION:
Calibration blocks required for the examination of welds in these vessels have r-' been fabricated from material of the same specification, product form, and f
( ,)s heat treatment as one of-the materials being joined as allowed by Article T-434.1.1 in the Winter 1976 Addenda of Section V of the ASME Boiler and Pressure Vessel Code.
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G 3-25
- ~ . . . . -. __ _ _
4.0 INSERVICE INSPECTION OF CLASS 3 CCMPONENTS The.following table provides a listing of the Class 3 pressure-retaining componerits (and their supports) which are subject to the inspection require-
~
ments of Subsection IWD of Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition, and Addenda through Summer, 1975.
This tabulation identifies the. components to be inspected, the component's safety class, the applicable code to which the component was built, and the :
method of examination. Relief from the inspection requirements of Subsec-tion IWD is requested in cases where these inspection requirements have been i
determined tc.be impractical. Where relief is requested, specific information is provided which identifies the applicable code requirements, justification for the relief request, and the inspection method to be used as an alternative.
The table groups the Class 3 pressure-retaining components (and their supports) on a system basis. Only those portions of the system which contain Class 3 pressure-retaining components (and their supports) are subject to the inspec-tion requirements of Subsection IWD.
i.
. As indicated in the tabulation, many of the' components included in this pro-gram were not built to the ASME Section III Code because it was not in effect j at the time the component was purchased. However, these components will be inspected in accordance with the requirements of Subsection IWD to the
- extent practical.
The abbreviations used within this table for " Codes Applicable To Construction" are defined as follows:
III-C- = ASME Boiler and Pressure Vessel Code-Section III, Class C VIII = ASME Boiler and Pressure Vessel Code-Section VIII P&V III = ASME Code for Pumps and Valves for Nuclear Power, Class I'I III-3 = ASME Boiler and Pressure Vessel Code-Section III, Class 3
. API 620 = American Petroleum Institute Recommended Rules for Design and Construction of Large, Welded, Low-Pressure Storage Tanks API 650 = American Petroleum Institute, Welded Steel Tanks for Oil MSS SP. = Manufacturers Standardization Society O.
4-1 4
7 , , - , . ~ . . , . , y , ~ , - - - , . , . _ - - .
FARLEY NUCLEAR PLANT. UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS
- CODE
' ANS APPLICABLE METHOD SECTION XI SAFETY TO OF CODE RELIEF COMPONENT CLASS CONSTRUCTION EXAMINATION REQUESTED SYSTEM River Pumps (5) 2b P & V III Visual / Operating Yes - 4.1.1 Water Pressure Piping 2b III - 3 Visual / Operating Yes - 4.1.3 Pressure 4.1.5 4.1.6 i
Hangers 2b III - 3 and Visual No MSS SP-58 MSS SP-69 Auxiliary Piping 2b III Visual / Operating Yes - 4.1.3 Steam Pressure 4.1.11 Hangers 2b III - 3 and Visual No MSS SP-58 MSS SP-69 1
Service Pumps (5) 2b P & V III Visual / Operating Yes - 4.1.l~
Water Pressure Strainers (2) 2b VIII Visual / Operating Yes - 4.1.5 Pressure Strainers (2) 2b III - 3 Visual / Operating Yes - 4.1.4 Pressure
- This applies to components identified as ANS Safety Class 2b - - . . _ _ _ _ _ _ - - _ - _ _ _ _ -
O~ O O .
FARLEY NUCLEAR PLANT - UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS
- CODE ANS APPLICABLE METHOD - SECTION XI SAFETY TO OF CODE RELIEF 4
COMPONENT- CLASS CONSTRUCTION EXAMINATION REQUESTED SYSTEM
- ervice Auxiliary Feedwater Pump Room 2b III - 3 Visual / Operating Yes - 4.1.9 Water Coolers (2) (Tubes Only) Pressure Battery Charging Room Coolers (3) 2b III - 3 Visual / Operating Yes - 4.1.9 (Tubes Only) Pressure 4
? Charging Pump Room Coolers (3) 2b III - 3 Visual / Operating Yes - 4.1.9
" (Tubes Only) Pressure CCW Pump Room Coolers (2) 2b III - 3 Visual / Operating Yes - 4.1.9 (Tubes Only) Pressure CTMT Spray Pump Room Coolers (2) 2b III - 3 Visual / Operating Yes - 4.1.9 (Tubes Only) Pressure 600 V Load Center Coolers (2) 2b III - 3 Visual /0Dwating Yes - 4.1.9 (Tubes Only) Pressure Diesel Generator Heat Exchangers 3 III - 3 Visual / Operating Yes - 4.1.5 Pressure Motor Control Center Room Coolers (2) 2b III - 3 Visual / Operating Yes - 4.1.9 (Tubes Only) Pressure RHR LHSI Pump Room Coolers (2) 2b III - 3 Visual / Operating Yes - 4.1.9 (Tubes Only) Pressure Charging Pump Bearing and Gear Oil 2b VIII Visual / Operating Yes - 4.1.4 Coolers (3) Pressun! ,
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LI FARLEY NUCLEAR PLANT - UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS
- CODE ANS APPLICABLE METHOD SECTION XI SAFETY TO OF CODE RELIEF SYSTEM COMPONENT CLASS CONSTRUCTION EXAMINATION REQUESTED Service Containment Coolers (4) 2b VIII Excess Flow Yes - 4.1.10 Water-~ (Tubes Only) Device Piping 2b III - 3 Visual / Operating Yes - 4.1.3 Pressure 4.1.4 4.1.5 4.1.6
[
Hangers 2b III - 3 Visual No MSS SP-58 MSS SP-69 Component Pumps (3) 2b P & V III Visual / Operating Yes - 4.1.5 Cooling Pressure Water 9 CCW Heat Exchangers (3) (Shell Side) 2b VIII Visual / Operating Yes - 4.1.7 ,
Pressure CCW Surge Tank 2b API 620 Visual / Operating No Pressure CVCS Letdown HX (Shell Side) 2b VIII Visual / Operating Yes - 4.1.7 Pressure CVCS Excess Letdown HX (Shell Side) 2b VIII Visual / Operating Yes - 4.1.7 Pressure CVCS Seal Water HX (Shell Side) 2b VIII Visual / Operating Yes - 4.1.7 Pressure
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l FARLEY NUCLEAR PLA T - UNIT NO. 2 INSERVICE INSPECTION 'ROGRAM ASME CODE CLASS 3 COMPONENTS
- CODE .
ANS APPLICABLE METHOD SECTION XI SAFETY TO OF CODE RELIEF SYSTEM COMPONENT CLASS CONSTRUCTION EXAMINATION REQUESTED Component RHR HX (2) (Shell Side) 2b VIII Visual / Operating Yes - 4.1.7 Cooling Pressure Water Spent Fuel Pool HX (2) (Shell Side) 2b VIII Visual / Operating Yes - 4.1.7 Pressure
?
R.C. Drain Tank HX (Shell Side) 2b III C Visual / Operating Yes - 4.1.7 Pressure Charging Pump Seal Coolers (3) 2b VIII Visual / Operating Yes - 4.1.4 Pressure RHR Pump Seal Coolers (3) 2b VIII Visual / Operating Yes - 4.1.4 Pressure Piping 2b III - 3 Visual / Operating Yes - 4.1.3 Pressure 4.1.5 Hangers 2b III - 3 and Visual No MSS SP-58 MSS SP-69 Auxiliary Pumps (3) 20 P & V III Visual / Hydro No Feedwater Condensate Storage Tank 2b III - 3 Visual / Operating No Pressure Piping 2b III - 3 Visual / Hydro No
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NJ L. N FARLEY NUCLEAR PLANT - UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS
? Control
- Boric Acid Filter 2b III C Visual / Hydro No Boric Acid Transfer Pumps (2) 2b P & V III Visual / Hydro No Boric Acid Blender 2b III - 3 Visual / Hydro No Piping 2b III - 3 Visual / Hydro No Boron Injection Surge Tank 2b III - 3 Visual / Operating No Pressure BIT Recirculation Pumps (2) 2b III - 3 Visual / Operating Yes - 4.1.5 Pressure Piping 2b III - 3 Visual / Operating Yes - 4.1.3 Pressure 4.1.5 Reactor Reactor Makeup Water Storage Tank 2b III - 3 Visual / Operating No Makeup Pressure Reactor Makeup Water Pumps (2) 2b III - 3 Visual / Operating Yes - 4.1.5 Pressure s
.s.
FARLEY NUCLEAR PLANT - UNIT NO. 2 INSERVICE INSPECTION PROGRAM ASME CODE CLASS 3 COMPONENTS * -
CODE-ANS APPLICABLE METHOD SECTION XI SAFETY TO OF ' CODE RELIEF COMPONENT CLASS CONSTRUCTION EXAMINATION REQUESTED SYSTEM Reactor Piping 2b III - 3 Visual / Operating Yes - 4.1.5 Makeup Pressure Hangers 2b III - 3 and Visual No MSS SP-58 MSS SP-69 Contain- Spray Additive Tank 2b VIII Visual / Operating Yes - 4.1.11 ment Spray Pressure Piping 2b III - 3 Visual / Operating Yes - 4.1.3 Pressure 4.1.11 Spent Spent Fuel Pool HX (2) (Tube Side) 2b III - C Visual .Yes - 4.1.8-Fuel Pool Spent Fuel Pool Pumps (2) 2b P & V III Visual / Operating Yes - 4.1.5 Cooling Pressure Piping 2b III - 3 Visual / Operating Yes - 4.1.3 Pressure 4.1.2 4.1.5 Hangers 2b III - 3 and Visual No MSS SP-58 MSS SP-69
-- 4.1 Request for Relief from ASME Section XI Requirements
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4.1.1 RELIEF REQUEST COMPONENT: River Water Pumps (5) CODE CLASS: 3 Service Water Pumps (5)
CXAMINATION REQUIREMENT:
IWD-2410 (b) and (c) require a visual examinacion for leakage either during a system inservice test or during hydrostatic pressure testing.
BASIS FOR RELIEF:
Due to component design and mounting details, the visual inspection of these vertical, centrifugal pumps is impractical except at the pump discharge nozzles.
ALTERNATIVE EXAMINATION:
Visual inspection of the discharge nozzles will be performed while the pumps are operating. The pump casings will be visually inspected each time the o pumps are removed for maintenance.
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4-8
4.1.2 RELIEF REQUEST COMPONENT: Buried piping in the Spent Fuel CODE CLASS: 3 Pool Cooling System EXAMINATION REQUIREMENT:
IWD-2600 (b) requires that in the case of buried components a system pressure test, in lieu of the visual examination, shall be conducted.
BASIS FOR RELIEF:
The design of this sy: tem does not include provisions for testing buried piping as required by IWD-2600 (b). Visual inspection for leakage at ground level is also impossible.
ALTERNATIVE EXAMINATION:
Leaktightness of all buried or encased piping will be demonstrated during normal system functional testing.
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- 4.1.3 RELIEF REQUEST COMPONENT: Piping 2" and smaller for the following systems: CODE CLASS: 3 River Water, Auxiliary Steam, Service Water, Component Cooling Water, Chemical and Volume Control, Containment Spray, and Spent Fuel Pool Ccoling.
EXAMINATION REQUIREMENT:
IWD-2410 (b) requires a visual examination for leakage on all components either during a system inservice test or during hydrostatic testing.
BASIS FOR RELIEF:
These smaller lines have wall thicknesses in excess of what ASME Section III requires for retaining internal pressure. Using bravier-walled piping in these small lines essentially means they are over-designed for the pressure they are retaining and are not susceptible to the type leakages found during hydrostatic testing.
<-'x
( ) System pressure tests will not be performed on lines 2" and smaller unless
'- they are connected to, and cannot be isolated from, larger lines designated to be pressure-tested.
ALTERNATIVE EXAMINATION:
All accessible piping 2" and smaller will be visually inspected at normal oper-ating pressure.
1
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v 4-10\
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\'- 4.1.4 -
RELIEF REQUEST COMPONENT: Equipment with primary connections 2" and CODE CLASS: 3 smaller in the following systems:
Service Water and Component Cooling Water.
EXAMINATION REQUIREMENT:
Same as 4.1.3 BASIS FOR RELIEF Same as 4.1.3 ALTERNATIVE EXAMINATION:
Equipment with primary connections 2" and smaller will be visually examined in accordance with Relief Request 4.1.3.
O 4-11{
_ . - - .- . . - - . - = ._.__-_ . . . _. - - .
J 4
S 1 s 4.1.5 RELIEF REQUEST C0tiPONENT: Portions of the following systems: CODE CLASS: 3 River Water, Service Water, Component Cooling Water, Chemical and Volume Control, Reactor Make-Up, and Spent Fuel Pool Cooling.
EXAMINATION REQUIREMENT:
IWD-2410 (b) requires a visual examination for leakage on all components either during a system inservice test or during hydrostatic testing. '
l BASIS FOR RELIEF:
! System pressure testing is impractical since these systems operate continuously l during all modes of plant operation, i
ALTERNATIVE EXAMINATION:
l
, s Functional operation of the systems demonstrate: structural and leaktight in-tegrity. Visual inspection to verify leaktightness will be performed while
=
the systems are at normal operating pressure.
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O 4-12'
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. 4.1.6 RELIEF REQUEST i i
COMPONENT: Buried piping in the River Water System CODE CLASS: 3 i and the Service Water System EXAMINATION REQUIniMENT:
IWD-2600 (b) requires that in the case of buried components a system' pressure ;
{ test, in lieu of the visual examination, shall be conducted. *
- c
- BASIS FOR RELIEF:
4 l .The design of these systems does not inc1;de provisions for testing buried l piping as required by IWD-2600 (b). -
ALTERNATIVE EXAMINATION:
I Buried piping will be inspected by conducting a visual observation of the ground (at ground elevation) for wet spots while the systems are at operating ;
~
} pressure. This~is in accordance with FSAR paragraphs 3.1.41 and 9.2.1.4.
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i= - . - . .. ._.-._- -. . - - - . - _ - . . . . . - . . - . - . -_..-
4.1.7- RELIEF REQUEST
. COMPONENT: Shell side of the following Heat Exchangers: CODE CLASS: 3 Component Cooling Water (3), CVCS Letdown, CVCS Excess Letdown, CVCS Seal Water, RHR (2), ,
Spent Fuel Pool (2), and R. C. Drain Tank HX. ,
EXAMINATION REQUIREMENT:
l Same as 4.1.5 BASIS FOR RELIEF:
Same as 4.1.5 ALTERNATIVE EXAMINATION:
Same-as 4.1.5
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C) 4-14
p 4.1. 8' RELIEF' REQUEST COMPONENT: Tube Side of the following: CODE CLASS: 3 Component Cooling _ Water Heat Exchangers (3)
Spent Fuel Pool Heat Exchangers (2) .
EXAMINATION REQUIREMENT:
IWD-2410 (b) and (c) require a visual examination for leakage either during a system inservice _ test or during hydrostatic pressure testing.
'8 ASIS FOR RELIEF:
Due to component design, the tubes of these heat exchangers cannot be visually inspected.
~ ALTERNATIVE EXAMINATION:
Tube side inspection will be performed by isolating the heat exchanger, remov-ing .the waterbox covers, and pressurizing the shell side with water. Tube O leakage is_ indicated if there is any flow from the tubes while in this con-figuration. This type inspection will'be performed at least once per inspec-tion interval.
6 .'
I 4-15
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's / 4.1.9 RELIEF REQUEST COMPONENT: Tubes in the following: CODE CLASS: 3 Auxiliary Feedwater Pump Room Coolers (2),
Battery Charging Room Coolers (3), ,
Charging Pump Room Coolers (3)
CCW Pump Room Coolers (2),
CTMT Spray Pump Room Coolers (2) 600 V Load Center Coolers (2),
Motor Control Center Room Coolers (2), and RHR/LHSI Pump Room Coolers (2).
EXAMINATION REQUIREMENT:
IWD-2410 (b) and (c) require a visual examinatien for leakage either during a system inservice test or during hydrostatic testing.
BASIS FOR RELIEF:
Due to component design, the tubes of these room coolers cannot be visually inspected.
'wl ALTERNATIVE EXAMINATION:
The normal operation of room coolers demonstrates their structural and leak-tight integrity. The coolers will be inspected by observing the cooler basin drain for any abnormal flow (other than normal condensation) while the coolers are operating.
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4-16',
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'- 4.1.10 RELIEF REQUEST COMPONENT: Tubes of the Containment Coolers (4) CODE CLASS: 3 EXAMINATION REQUIREMENT:
IWD-2410 (b) and (c) require a visual examination for leakage either during a system inservice test or during hydrostatic testing.
BASIS FOR RELIEF:
Due to component design, the tubes of these air coolers cannot be visually inspected.
ALTERNATIVE EXAMINATION:
The normal operation of the containment air coolers demonstrates their struc-tural and leaktight integrity. Visual inspection to verify leaktightness will be performed while the system is at normal operating pressure.
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4-17 \
I
4.1.11 RELIEF REQUEST COMPONENT: Auxiliary Steam System Piping, CODE CLASS: 3 Spray Additive Tank and Containment Spray System Piping.
EXAMINATION REQUIREMENT:
IWD-2410 (b) requires a visual examination for leakage either during a system inservice test or during hydrostatic testing.
BASIS FOR RELIEF:
No practical means of isolating these systems exists: tnerefore, system pressure tests cannot be performed.
ALTERNATIVE EXAMINATION:
Visual inspection to verify leaktightness will be performed while the systcms are at normal operating pressure.
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i 4-18'