ML19345F957
| ML19345F957 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/11/1981 |
| From: | TEXAS UTILITIES SERVICES, INC. |
| To: | |
| Shared Package | |
| ML19345F955 | List: |
| References | |
| PROC-810211, NUDOCS 8102190606 | |
| Download: ML19345F957 (72) | |
Text
m COMANCHE PEAK u
STEAM ELECTRIC STATIO N UNIT NO.1
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e DOCKET NO. 50-445 PRESERVICE INSPECTION PROGRAM FOR CLASS 1,2, AND 3 COMPONENTS
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i COMANCHE PEAK STEAM ELECTRIC STATION UNIT N0. 1 PRESERVICE INSPECTION PROGRAM for O Class 1, 2 and 3 Components i
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O TABLE OF CONTENTS
1.0 INTRODUCTION
- . ................... 1-1 2.0 CLASS 1 COMPONENTS . . . . . . . . . . . . . . . . . . . . . . 2-1 3.0 CLASS 2 COMPONENTS . . . . . . . . . . . . . . . . . . . . . . 3-1 4.0 CLASS 3 COMPONENTS . . . . . . . . . . , , , , , , , , , , , 4,7 O
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TEXAS UTILITIES GENA.ATING COMPANY COMANCHE PEAR, UNIT 1 PRESERVICE INSPECTION The attached tables provide a listing of the Class 1, 2, and 3 pressure-retaining components (and their supports) which are subject to the inspection requirements of Subsection IWB, IWC and IWD of Section XI of the ASME Boiler and Pressure Vessel Code,1974 Edition, and Addenda through Summer, 1975.
These tabulations identify the components to be inspected, the component safety class and code reference and the method of examination. Relief from the inspection requirements of each Subsection is requested in cases where these inspection requirements have been determined to be impractical. Where relief is requested, specific information is provided which identifies the applicable code O requirement, justificet4on for the reifef regeest, end the inspect 4on method to be used as an alternative.
The piping pressure boundaries for Class 1 systems subject to the examination requirements of IWB-2500 Category B-J are identified in Table 1. Portions of systems exempt from examination by IWB-1220 and which will be subject to visual exanination for evidence of leakage during system hydrostatic test under category IWB-2500 B-P are identified in Table 2.
Portions of Class 2 systems exempt from examination by IWC-1220 will be subject to visual examination for evidence of leakage during system hydrostatic test under category IWA-5000 and IWC-5000.
The piping pressure boundaries for Class 2 systems which recirculate reactor coolant, and are subject to the examination requirements of IWC-2520 C-F, are identified in Table 3. Class 2 systems which O recirculate other than reactor coolant, and are subject to the 1-1
O examination requirements of IWC-2520 C-G, are identified in Table 4.
As defined by article IWC-2411 for Class 2 components, the examinations required by IWC-2520 may be divided among the ntzaber of components of the same size and geometry in each of the multiple streams of a systen which perform the same functions. This criteria will be utilized in selecting Class 2 system pipe welds for examination. As required by IWC-2520 Categories C-F and C-G, piping system circisaferential welds to be selected for examination are only those at geometric discontinuities and includes 100 percent of those in systems recirculating reactor coolant and 50 percent of those of systems containing other than reactor coolant.
Under the provisions of 10CFR 50.55a (g) exception may be taken to the examination requirements which are detenained to be impractical.
Attached are specific requests for relief for those areas where exaaination requirements are known to be impractical and relief is Q requested from meeting the requirements of Section XI of the ASME Boiler and Pressure Vessel Code.
The preservice inspection programs outlined in the attached tabulations have been developed as a result of a design review. Should certain ASME Section XI Code requirements be discovered to be impractical due to unforeseen reasons during the process of perfonaing inspections or tests, relief will be requested from the specific Section XI Code requirement at that time.
Ultrasonic examinations will be conducted in accordance with the provisions 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 for ultrasonic examination of piping systems.
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O It is recognized tht Appendix III of Section XI was issued in the l Winter,1975, Addenda and, as such, has not been officially recognized by the NRC by reference in 10CFR50. However, Appendix III is the first !
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guideline that has been published in the ASME Codes for the ultrasonic
! examination of pipe welds and, as such, its use is essential. l
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As an alternative for I-3121 of Section XI " Calibration blocks required for the examination of welds in ferritic vessels 21/2 inches thick and 4
over will be fabricated from material of the same specification, I 1
product fom, and heat treatment as one of the paterials being joined as allowed by article T-434.1 in the Winder,1976 Addenda of Section V j of the ASME Boiler and Pressure Vessel Code."
The reason this alternative is requested is that the Code requires that calibration blocks for the examination of welds in ferritic vessels 2 1/2 inches thick and greater be f abricated from material taken from the component nozzle drop out or material from the component. If naterial lO I
from the component is not available, material of the see specification and product fom may be utilized.
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However, it is required that the acoustic velocity and attenuation of I l such a block be demonstrated to f all within the range of straight beam i
j longitudinal wave velocity and attenuation found in the unciad
- components.
For the components in the Comanche Peak Plant, particularly the l pressurizer and steam generators, it will be impossible to meet the requirements of either of these alternatives.. Materials of the specification are readily available, but because all the components 4 involved are clad on the inner surfaces, it would be impossible to i
obtain a comparison of sound beam velocities and attenuations in the
, unclad component. Therefore, for ultrasonic examination of components with cladding, clad calibration blocks will be used.
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< Limitations may occur for the examination of piping system circtnferential but welds (Category B-J) when the welds occur at geometric discontinuitie.s 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 perfomed 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, examination can be performed from the fitting side except where the intrados of the fitting prevents adequate ultrasonic coupling. No examinations can be j perfomed from the fitting side when it is a valve or a flange. In all cases 100 percent of the weld material can be examined.
In instances where the locations of pipe supports or hangers restrict the access available for the examination of pipe welds as required by IWB-2600, examinations will be performed to the extent practical unless removal of the support is pemissible without unduly stressing the O system.
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O 1AstE 1 COMANCHE PEAK NUCLEAR PLANT Class 1 systems piping pressure boundaries for piping in examination category IWB-2500-B-J.
Loop 1:
(1) RHR system 12 inch take off to valve 8701A and hot leg high head injection 6 and 2 inch line to check valve 8905A.
(2) Reactor coolant 2 inch hot leg and cold leg RTD manifold lines and 3 inch return line.
(3) Chemical and volume control system 3 inch alternate charging line to check valve 8379B.
(4) Waste disposal system 2 inch reactor coolant drain line to valve 8058A.
(5) Safecy injection system 10 inch acctsnulator discharge line to check valve 8956A, RHR 6 inch low head injection line to check valve 8818A and 2 inch cold leg high injection line to check yalye 8819A.
(6) Safety injection 11/2 inch boron injection line to valve 8810A.
(7) Reactor coolant system 4 inch spray line to 6 x 4 inch reducer.
Loop 2:
(1) Hot leg high head injection 6 and 2 inch line to check valve 8905A and 6 inch low head injection to check valve 8841A.
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4 (2) Reactor coolant 2 inch hot leg and cold leg RTD manifold lines l and 3 inch return line.
(3) Waste disposal system 2 inch reactor coolant drain line to valve 8058B.
l l (4) Safety injection system 10 inch accunulator discharge line to j valve 8956B, RHR 6 inch low head injection line to check valve 8818B and 2 inch cold leg high head injection to check valve l
88198.
j (5) Safety injection 11/2 inch boron injection line to valve 8810B.
Loop 3:
(1) Hot leg high head injection 6 and 2 inch line to check valve 8905C and 6 inch low head injection to check valve 88418.
(2) Reactor coolant 2 inch hot leg and cold leg RTD manifold lines i
and 3 inch return line.
(3) Chemical and volume control system 3 inch letdown line to valve <
I LCV-459 and reactor coolant 2 inch drain line to valve 8058C.
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! (4) Safety injection system 10 inch accunulator discharge line to valve 8956C RHR 6 inch low head injection line to check valve 8818C and 2 inch cold leg high head injection line to check valve 8819C.
(5) Safety injection 11/2 inch boron injectio line to valve 8810C.
1 Loop 4:
(1) RHR 14 inch take off to valve 87108, high head injection 6 and 2
- O inch iine to check veive 8905C.
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(2) Reactor coolant 2 inch hot leg and cold leg RTD manifold lines and 3 inch return line.
(3) Reactor coolant 14 inch surge line to pressurizer.
l (4) Reactor coolant system 6 inch lines to pressurizer safety valves
! 8010 A, B and C.
(5) Reactor coolant system 3 and 6 inch lines to pressurizer safety relief valves PCV-445A and PCV-456.
(6) Waste disposal system 2 inch reactor coolant drain line to valve 80580.
(7) Chemical and volume control system 3 inch normal charging line to check valve 8378B.
O (8) Sefety iaaectioa system 10 inch ecc <>uietor discherse iine to valve 89560, RHR 6 inch low head injection line to check valve 8818D and 2 inch cold leg high head injection to check valve 8819D.
(9) Safety injection 11/2 inch boron injection line to valve 8810D.
(10) Reactor coolant system 6 and 4 inch spray line to pressurizer.
Safety Injection System:
! (1) Boron Injection 3 and l' 1/2 inch lines from valves 8810A, B, C and D to check valve 8815, Chemical and Volume Control System:
(1) Reactor coolant system 2 inch auxiliary spray line from valve
'Q 8145.
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j g (2) Reactor coolant pump 2 and 1 1/2 inch seal injection water lines !
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i to check valves 8367A, B, C and D. L i
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TABLE 2 COMANCHE PEAK NUCLEAR PLANT Class 1 systems piping and components which are exempted from examination by IWB-1220 and require examination under category IWB-2500 B-P.
(1) Reactor coolant temperature element wells, TE 413A, 413B, 423A, 423B, 433A, 433B, 443A and 4438.
(2) Reactor coolant 1 inch hot leg RTD take off lines.
(3) Reactor coolant RTD loop temperature element wells TE 410A, 4108, 411A, 411B, 420A, 4208, 421A, 421B, 430A, 430B, 431A, 431B, 440A, 440B, 441A and 4418.
(4) Chemical and volume control 1 inch excess letdown line to valve 8153.
(5) Reactor vessel head 1 inch vent line to blind flange.
(6) Reactor vessel lower head in core instrumentation conduits.
(7) Reactor coolant pump 3/4 inch seal by-pass lines to flow orifices.
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O TABLE 3 -
j COMANCHE PEAK NUCLEAR PLANT a
j Class 2 systems piping pressure boundaries requiring examination under category IWC-2530 C-F.
1 (1) Train A 16 and 14 inch suction line from valve 8701A to Pump No.
I 1 and recirculation sump 16 and 14 inch suction line to valve 8811A.
1 (2). Train A 12,10 and 8 inch discharge line from Pump No. I to Heat Exchanger No.1 inlet and 8 inch heat exchanger by-pass line to
! valve FCV-618.
l (3) Train A 12 and 10 inch discharge line from Heat Exchanger No.1 outlet to valve 8761A,10 and 6 inch low head injection to Loops 1 and 2 cold legs up to valves 8818A and B, 8 inch line to-charging pump suction to check valve 8968A and 8 inch by-pass ,
j line to valve FCV-618.
(4) Train B 16 and 14 inch suction line from valve 8701B to Pump No.
I and recirculation sump 16 and 14 inch suction line.tc valve 8811B.
(5) Train B 12,10 and 8 inch discharge line from Punp No.1 to Heat Exchanger No. 1 inlet and 8 inch heat exchanger by-pass line to i valve FCV-619.
(6) Train B 12 and 10 inch discharge line from Heat Exchanger No.1 outlet to valve 8716B,10 and 6 inch low head injection to Loops 3 and 4 cold legs up to valves 8818C and D, 8 inch line to safety injection pump suction to valve 88048, and 8 inch by-pass line to O vaive FCV-619.
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O (7) RHR 10 and 6 inch hot leg injection to check valves 8841A and B and 8 inch RWST return line to valve 8717.
Chemical and Volume Control (1) Charging pump 8 and 6 inch suction from 8 x 4 inch reducer in outlet line from VCT to inlets of pumps, 8 inch, suction from RHR to check valve 8969A, 8 inch suction from SIS pumps to valve -
88048 and 8 inch suction from RWST to valves LCV 112D and E.
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TABLE 4 COMANCHE PEAK NUCLEAR PLANT Class 2 systems piping pressure boundaries requiring examination under category IWC-2520 C-G.
Main steam (1) Loop 1, 32 inch line from steam generator to power operated stop valve HV 2333A, inch drain pot, 8 inch line to power operated relief valve PV 2325 and 6 inch branch connections to safety relief valves MS-021, 022, 023, 024 and 025.
(2) Loop 2, 32 inch line from steam generator to power operated stop valve HV 2334A, inch drain pot, 8 irch line to power operated relief valve PV 2326 and 6 inch branch connections to safety relief valves MS-058, 059, 060, 061 and 062.
O (3) Loop 3, 32 inch line from steam generator to power operated stop valve HV2335A, inch drain pot, 8 inch line to power operated relief valve PV 2327 and 6 inch branch connections to safety relief valves MS-033, 034, 035, 036 and 037.
(4) Loop 4, 32 inch line from steam generator to power operated stop valve HV 2336A, inch drain pot, 8 inch line to power operated
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relief valve PV 2378, and 6 inch branch connections to safety relief valves MS-129,130,131,132 and 133.
Main feed (1) Loop 1,18 and 16 inch line from steam generator to check valve FW-082.
(2) Loop 2,18 and 16 inch line from steam generator to check valve FW-074.
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(3) Loop 3,18 and 16 inch line from steam generator to check valve FW-070.
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(4) Loop 4, 18 and 16 inch line from steam generator to check valve 3 FW-088. !
- Safety Injection System 1
) The boundaries requiring inspection will be included in a later >
4 revision.
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Containment Spray System i
a The boundaries requiring inspection will be included in a later
! revision.
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] PRESERVICE EXAMINATIONS OF CLASS 1 SYSTEMS AND COMPONENTS FOR COMANCHE PEAK NUCLEAR PLANT UNIT #1 IWB TABLES 2600 2500 EXAMINATION ITEM CAT. COMP 0NENT VOL. SURF. VIS.
REACTOR VESSEL Bl.1 B-A Middle Shell Course to Lower Shell Course X - -
Circumferential Weld Bl.1 B-A Upper Shell Course Longitudinal Welds X - -
O Bl.1 B-A Middle Shell Course Longitudinal Welds X - -
Bl.1 B-A Lower Shell Course Logitudinal Welds X - -
Bl.2 B-B Upper Shell Course to Middle Shell Course X - -
Circumferential Weld 81.2 B-B Lower Head to Shell Weld X - -
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Bl.2 B-B Upper Head Meridional Welds X - -
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Bl.2 B-B Lower Head Ring to Disc Circunferential X - -
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Weld j l
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,1WB TABLES 2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
Bl.2 B-B Closure Head Ring to Disc Circumferential X - -
[
Weld ;
Bl.2 B-B Lower Head Ring Meridional Welds X - -
Bl.3 B-C Vessel to Flange Weld X - -
l Bl.3 B-C Closure Head to Flange Weld X - -
Bl.4 B-D Inlet Nozzle to Shell Welds X - -
r Bl.4 B-D Outlet Nozzle to Shell Welds X - -
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() B1.5 B-E Vessel Penetrations, Including Control Rod - -
11 Drive Penetrations and Control Rod Housing Pressure Boundary Welds Bl.6 B-F Primary Nozzle to Safe End Welds X R -
Bl.7 B-G-1 Closure Studs, in Place - -
12 <
Bl.8 B-G-1 Closure Studs and Nuts, When Removed R X - ;
Bl.9 B-G-1 Vessel Flange Ligaments X - - i Bl.10 B-G-1 Closure Stud Washers -- - X Bl.11 B-G-2 Pressure Retaining Bolting - - X Bl.12 B-H Vessel Supports (Integrally Welded) 1 - -
O Bl.13 B-I-1 Closure Head Cladding R R R 2-2 i
pa IWB TABLES 2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
Bl.14 B-I-1 Vessel Cladding - -
R Bl.15 B-N-1 Interior Surface of Vessel and Internals - -
X Bl.16 B-N-2 Interior Attachments and Core Support - -
14 Structures 81.17 B-N-3 Core Support Structures - -
15 Bl.18 B-0 Control Rod Drive Housing R - -
B1.19 B-P Exempted Components - -
11 PRESSURIZER B2.1 B-B Pressurizer Shell Welds X - -
B2.2 B-D Nozzle to Vessel !l elds R - -
B2.3 B-E Heater Penetrations - - 11 B2.4 B-F Nozzle to Safe-End Welds R X -
B2.5 B-G-1 Pressure Retaining Bolts and Studs, In Place 2 - -
82.6 B-G-1 Pressure Retaining Bolts and Studs, When 2 2 -
Removed B2.7 B-G-1 Pressure Retaining Bolting - - 2 v
B2.8 B-H Integrally Welded Vessel Supports X - -
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2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
B2.9 B-I-2 Vessel Cladding - -
R B2.10 B-P Exempted Components - -
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B2.11 B-G-2 Manway Bolting - -
X 5
STEAM GENERATORS (PRIMARY SIDE) i i
B3.1 B-B Channel Head to Tubesheet Weld X - -
- B3.2 B-D Nozzle-to-Vessel Head Welds and Nozzle 3 - -
Q Inside Radiused Section B3.3 B-F Nozzle to Safe End Welds R X' -
1 B3.4 B-G-1 Pressure Retaining Bolts and Studs, In Place 4 - -
4 B3.5 B-G-1 Pressure Retaining Bolts and Studs, When 4 4 -
Removed i
- B3.6 B-G-1 Pressure Retaining Bolting - -
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B3.7 B-H Integrally Welded Vessel Supports 5 - -
B3.8 B-I-2 Vessel Cladding - -
R i
B3.9 B-P Exempted Components - -
11 83.10 B-G-2 Manway Bolting ,
-- - X 2-4
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IWB TABLES 2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
PIPING SYSTEMS
! B4.1 B-F Safe End to Pipe Weld 16 16 -
.j j B4.2 B-G-1 Pressure Retaining Bolts and Studs, In Place 6 - -
84.3 B-G-1 Pressure Retaining Bolts and Studs, When 6 6 -
Removed
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84.4 B-G-1 Pressure Retaining Bolting - -
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Bd.5 B-J Circumferential and Longitudinal Pipe Welds R - -
l B4.6 B-J Branch Pipe Connection Welds > 6" R - -
1 B4.7 B-J Branch Pipe Connections Welds 6" diameter -
X -
and smaller B4.8 B-J Socket Welds -
X .-
B4.9 B-K-1 Integrally Welded Supports R - -
B4.10 B-K-2 Supports Components - - 15 l
B4.11 B-P Exempted Components - -
11 B4.12 B-G-2 Pressure Retaining Bolting - - X
! REACTOR COOLANT PUMPS
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B5.1 'B-G-1 Pressure Retaining Bolts and Studs, In' Place- R - -
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, 2-5'
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l O iw8 Tx8LES 2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
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B5.2 B-G-1 Pressure Retaining Bolts and Studs, When R X -
Removed l
B5.3 B-G-1 Pressure Retaining Bolts - -
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B5.4 B-K-1 Integrally Welded Supports 7 - -
B5.5 B-K-1 Support Components - - X l
1 B5.6 B-L-1 Pump Casing Welds 15 - -
i B5.7 B-L-2 Pump Casing - -
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O B5.8 B-P Exempted Components - -
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B5.9 B-G-2 Pressure Retaining Bolting - -
8 VALVES B6.1 B-G-1 Pressure Retaining Bolts and Studs In Place 9 - -
B6.2 B-G-1 Pressure Retaining Bolts and Studs, When 9 9 -
Removed B6.3 B-G-1 Pressure Retaining Bolts - -
9 B6.4 B-K-1 Integrally Welded Supports 10 - -
B6.5 B-K-2 p)
Support Components - -
X B6.6 B-M-1 Valve Body Welds 16 - -
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g IWB TABLES 2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
B6.7 B-M-2 Valve Bodies - -
15 B6.8 B-P Exempted Components - -
11 B6.9 B-G-2 Pressure Retaining Bolting - -
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O COMANCHE PEAK NUCLEAP, PLANT UNIT #1 PRESERVICE EXAMINATIONS CLASS-1 NOTES X - indicates the Code required examination which will be conducted R - indicates relief is requested. Reference attached.
Numbers relate to the tabulations of inspection requirements for the ,
Class 1 components to identify items where the examination requirements of Table IWC-2600 are not applicable. Specific details are:
(1) The reactor vessel is suported by pads integral with the primary i
nozzles and are excluded from the examination requirements of IWB-2500 Category B-H.
O (2) The pressurizer does not contein eny pressure retein4ng boiting equal to, or greater than, 2 inch diameter and no examinations are required for Items B2.5, B2.6 and B2.7.
(3) The steam generator primary nozzles are integrally cast with the vessel channel head and no examinations are required of nozzle to vessel welds for Item B3.2.
(4) The steam generator does not contain any pressure retaining bolting equal to, or greater than 2 inch diameter and no examinations are required for Items B3.4, B3.5 and B3.6.
J (5) The steam generator support is integrally forged with the tube sheet and no examinations are required for Item B3.7.
(6) The piping pressure boundary does not contain any pressure retaining bolting equal to, or greater than, 2 inch diameter and O no exemiaetioas are required for items 84 2. 84 3 ead 84 4-2-8
- -..~. ._ _ ._, __. _ __ _ _ _-- ..
i (7) The reactor coolant pump support brackets are integrally cast l
l with the pump casing and there are no examinations required for Item B5.4.
(8) The reactor coolant pump does not contain any pressure retaining bolting less than 2 inches diameter and no examinations are required for Item B5.9.
j (9) Valves in the Class 1 systems do not contain any pressure retaining bolting equal to, or greater than, 2 inch diameter and no exaninations are required for Items B6.1, B6.2 and B6.3.
(10) There are no integrally welded supports on valves and no examinations are required for Item B6.4.
(11) Visual examination for leaks during hydrostatic tests and during l
system leakage test prior to startup will statisfy these requirements.
- (12) Bolting will be removed. This item is not applicable.
(13) The reactor vessel is supported by pads integral with the primary
. nozzles and are excluded from the examination requirements of this category.
. (14) This category is relative to " Direct Cycle Boiling Water Type" and is not applicable.
(15) Shop and field examination and installation records will be used i to satisfy preservice examination requirements of items in this category.
(16) There are no components, parts or areas subject to examination that are applicable to the category of this item number.
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RELIEF REQUEST l l
O COMP 0NENT: Reactor Vessel CODE CLASS: 1 l
i EXAMINATION REQUIREMENT:
Tables IWB-2500 Category B-F and IWB-2600 Item Bl.6 require volumetric l l and surface examination of the nozzle to safe end weld and adjacent j base metal for one wall thickness on either side of the weld.
1 BASIS FOR RELIEF:
The design of the permanent insulation around the nozzle prevents surface examinations being performed on the base metal on the nozzle side of the weld to the extent required by IWB-2500 Category 8-F. The nozzle configuration is shown in Fig. Bl.2.
p figure IWB-3524.1 as published in the Summer 1974 Addenda reduced the V requirement for examination of adjacent base metal to 1/2t but the change was not reflected in Table IWB-2500.
ALTERNATIVE EXAMINATION:
The weld and required amount of base metal on each side of the weld will be ultrasonically examined from inside the nozzle utilizing remotely operated tooling. Additionally, the weld, base metal on the pipe side, and base metal on the nozzle side to the extent practical will be examined by ultrasonic and surface techniques from the outside surface.
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".._--_.-._ _ _ . _ . . _ . - . - . . _ _ . . ~ _ . . - . _ . _ - . . . _ . _ . . _ . - . . , . _ . _ _ . . _ _ . . . . , _ _ , - . . , . . - _ - ___
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l COMANCHE PEAK S.E.S. ;
g UNIT I V
N0ZZLE TO SAFE END WELD ACCESS 2-11 FIGURE B l.6 -
RELIEF REQUEST O COMPONENT: Reactor Vessel CODE CLASS: 1 I
l EXAMINATION REQUIREMENT.
l Tables IWB-2600 Item Bl.8 and IWB-2500 Category B-G-1 require a volumetric and surface examination of the reactor vessel head studs and nuts when removed.
BASIS FOR RELIEF:
Due to the inherent geometry of threaded fasteners and signal interference from threads, volumetric examinations do not provide meaning results. Ultrasonic tests will not provide the needed information on axial running defects in nuts. These are the only
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defects that would reduce the components ability to perform its intended function.
ALTERNATIVE EXAMINATION:
The required surface examination will be performed.
O 2-12
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RELIEF REQUEST
(:)
COMPONENT: Reactor Vessel CODE CLASS: 1 i
EXAMINATION REQUIREMENT:
i Tables IWB-2600 Items Bl.13 and Bl.14 and IWB-2500 Category B-I-1 require volumetric, surface and visual examination of the closure head cladding and a visual inspection of the vessel cladding.
I BASIS FOR RELIEF:
. The desig, of the vessel provides for the stress loads to be adequately accommodated by ferritic base material which is examined volumetrically j as required by other examination categories. Additional technical guidance is provided by later editions of Section XI where cladding examinations are no longer required.
C:)
l l ALTERNATIVE EXAMINATION:
l None O
2-13
RELIEF REQUEST O
COMP 0NENT: Reactor Vessel CODE CLASS: 1 EXAMINATION REQUIREMENT:
Tables IWB-2600 Item Bl.18 and IWB-2500 Category B-0 require volunetric examination of the control rod drive (CRD) housing welds.
BASIS FOR RELIEF:
The materials of construction in the CRD housing welds consist of 304 stainless steel welded to SB-167 inconell.
Because of the inherent coarse grain struction in the welds of these austenitic materials, ultrasonic examination may be subject to marked variations in attenuation velocity, reflection, and refraction at grain boundaries, as is stated in Article III, Supplement 7 of Section XI, 1977 Edition.
In the latest approved Code as specified in section 50.55a(g) of 10CFR Part 50 ASME Section XI 1977, with Addenda through Suntaary 1978 - Table IWB-2500-1 Examination Category B-0 Item B14.10, the specfied examination method is optional as either Volunetric or Surface.
ALTERNATIVE EXAMINATION:
To avoid the recognized inherent problems associated with ultrasonic examination of these austenitic assemblies, and to conduct preservice
- examinations by the method expected to be employed for subsequent inservice examinations, we propose the examination method for the Category B-0 CRD housing welds be Surface, in lieu of the required Vol uaetric.
O 2-14
RELIEF REQUEST O
COMPONENT: Pressurizer CODE CLASS: 1 EXAMINATION REQUIREMENT:
Tables IWB-2500 (ategory B-D and IWB-2600 Item B2.2 require volumetric examination of the nozzle to vessel welds and adjacent base metal for one wall thickness 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 by IWB-2600. Examinations will be performed from both the weld and shell surfaces. The nozzle configuration is shown in Figure B2.2.
O ALTERNATIVE EXAMINATION:
One hundred percent of the weld, the heat affected zone and the required amount 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.
O 2-15
l l
O l i
I I
l NOZZLE FORGING
- 5 1
. I VESSEL l HEAD ;
I 7 N ;
WELD DEPOSITED CLADDING l
l l
COMANCHE PEAK S.E.S.
UNIT I Q
PRESSURIZER N0ZZLE TO j VESSEL WELD CONFIGURATION l 2-16 FIGURE B 2.2 f
RELIEF REQUEST O
! COMPONENT: Pressurizer CODE CLASS: 1 EXAMINATION REQUIREMENT:
Tables IWB-2600 Item B2.4 and IWB-2500 Category B-F require a volumetric and surface examination of the pressurizer nozzle to safe end welds, including one wall thickness beyond the edge of the weld.
.l i BASIS FOR RELIEF:
The geometric configuration of the nozzle prevents ultrasonic examinations from being performed on the base metal on the nozzle side of the weld to the extent required by IWB-2500.
1
() ALTERNATIVE EXAMINATION:
One hundred percent of the weld volume and the required amount of base j metal on the pipe side of the weld will be examined. The base metal on the nozzle side of the weld will be examined to the extent practical.
I Surface examinations will be performed on essentially 100 percent of the required area.
i J
M I '2-17
RELIEF REQUEST COMPONENT: Pressurizer and CODE CLASS: 1 Steam Generators (4)
EXAMINATION REQUIREMENT:
Tables IWB-2600 Items B2.9 and B3.8 and IWB-2500 Category B-I-2 require visual examination of pressurizer and stean generator vessel cladding.
BASIS FOR RELIEF:
The design of the vessels provides for stress loads to be adequately accommodated by ferritic base material which is examined volunetrically as required by other examination categories. Additional technical guidance is provided by later editions of Section XI where cladding examinations are no longer required.
ALTERNATIVE EXAMINATION:
None
-G V
2-18
O REtiEF aEauES1 COMP 0NENT: Steam Generators (4) CODE CLASS: 1 EXAMINATION REQUIREMENT:
Tables IWB-2600 Item B3.3 and IWB-2500 Category B-F require surface and volmetric examinations of the nozzle-to-safe-end welds and adjacent base metal for one wall thickness on either side of the welds.
BASIS FOR RELIEF:
The geometric configuration of the nozzle prevents ultrasonic examinations from being performed on the base metal on the nozzle side of the weld to the extent required by IWB-2500.
O ALTERNATIVE EXAMINATION:
100 percent of the weld ulume and the base metal on the pipe side of the weld will be volmetrically examined. Volmetric examination of the base metal on the nozzle side will be conducted to the extent practical. Surface examinations will be perfomed on essentially 100 percent of the required area.
O 2-19
RELIEF REQUEST O COMPONENT: Piping Systems CODE CLASS: 1 EXAMINATION REQUIREMENT:
Tables IWB-2600 Item B4.5 and IWB-2500 Category B-J requires volumetric exanination of the longitudinal and circunferential welds including the base metal from one wall thickness beyond the edge of the weld.
BASIS FOR RELIEF:
The configuration of the piping system and components are such that limitations may occur for the volunetric examinations of circunferential butt welds, when the welds occur at geometric discontinuities such as pipe-to-vessel welds, pipe-to-fitting welds, and fitting-to-fitting welds. For pipe-to-fitting or pipe-to-vessel nozzle welds, volunetric examinations can be perfonned to the extent
' required by T-532 of section V from the weld and pipe surfaces.
Volunetric examination from the fitting side will depend on the geometric configuration. Where elbows and tees are concerned, volunetric examination can be performed from the fitting side except when the intrados of the fitting prevents adequate ultrasonic coupling.
No volunetric examinations can be perfonned on the fitting side when the fitting is a valve or a flange. In almost all cases 100 percent of the weld material can be exanined. In instances where welds occur at fitting-to-fitting, access restrictions as outlined above occur at both sides of the weld.
ALTERNATIVE EXAMINATION:
Volumetric examination will be performed on 100 percent of the weld volune and on the heat affected zone and base metal to extent p practicable. In those instances where ultrasonic examinations cannot
'd 2-20 J
RELIEF REQUEST be perfomed on 100 percent of the volume of the weld and heat affected zones, surface examinations will be perfonned, where possible, to supplement the limited volumetric examination.
i O
l l
l O
2-21
. _ . . _ _ . _ _ _ _ _ _ . ~ . _ . _ .
j RELIEF REQUEST O CODE CLASS:
4 COMPONENT: Piping Systems 1 EXAMINATION REQUIREMENT:
Tables IWB-2500 Category B-J and IWB-2600 Item B4.6 requires volumetric examination of branch pipe connection welds exceeding 6 inches diameter.
- BASIS FOR RELIEF
The configuration of the pipe branch connectors prevents 100 percent volunetric examination of the welds and heat affected zones. Practical alternative techniques to volumetrically examining the entire areas of these welds which would produce meaningful results are not presently available.
O ALTERNATIVE EXAMINATION:
A volumetric examination will oe performed where t'he results are meani ngf ul . A surface examination will be parfonned as a substitute for tbc.se areas where meaningful results cannot be obtained vol unetrically.
2-22 d l
1 l
I O aEtiEF aEauEST COMPONENT: Piping Systems CODE CLASS: 1 EXAMINATION REQUIREMENT:
Tables IWB-2500 Category B-K-1 and IWB-2600 Item B4.9 require volunetric examination 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 system integrally welded supports are attached to the pipe by fillet welds. The configuration of such welds is such that only the base material of the pipe wall can be examined by ultrasonic techniques. The postulated failure for a fillet weld attachment is
'Q that cracking would initiate at the toe of the weld and as such would be most readily detected by surface examination.
1 ALTERNATIVE EXAMINATION:
Surface examination will be performed-on the integrally welded attachnents to supplement the limited volumetric examination.
4 O
2-23
RELIEF REQUEST O ~
COMPONENT: Reactor Coolant Pumps (4) CODE CLASS: 1 EXAMINATION REQUIREMENT:
1 Table IWB-2600 Item B5.1 requires volumetric examination of the seal housing bolting while in place.
i i
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 perfonned when the bolting is in place.
ALTERNATIVE EXAMINATION:
Volumetric and surface examinations. will be performed as required by 4
IWB-2600 Item B5.3 when the seal housing is disassembled for maintenance.
4
]
-O -
1 I 2-24 .
RELIEF REQUEST
(]}
COMPONENT: Reactor Coolant Pumps (4) CODE CLASS: 1
- EXAMINATION REQUIREMENT:
Table IWB-2600 Item B5.2 requires volunetric and surface examinations of the pump main flange closure bolts when removed.
j BASIS FOR RELIEF:
Removal of the bolts for examination would require detensioning the fastenings and violation of the pump pressure boundary integrity.
4 ALTERNATIVE EXAMINATION:
4 O The main flange bolting will be examined as required by IWB-2600, Item B5.2 whenever a pump is disassembled for maintenace or at the end of the ten year interval when a punp will be disassembled for the performance of examination required by Category B-L-1.
4 l
i 2-25 1
.c w - y y4.+,vg--- i---u- 'r e wes es-- w e's ----- ' = e- * -**+'W -
e- = ** - e- -*- -'e- 9 -~<v + *+w 9 * -r
- r RELIEF REQUEST U)
COMPONENT: Reactor Coolant Pump Flywheels (4) CODE CLASS: N/A EXAMINATION REQUIREMENT:
Regulatory Guide 1.14 requires a surface exanination of all accessible surfaces of Reactor Coolant Flywheels.
BASIS FOR RELIEF:
The Reactor Coolant Flywheels are painted; thus, surface exaninations is not practical.
ALTERNATIVE EXAMINATION:
('T '
Volumetric examination will be performed as requested by Regulatory Guide 1.14.
,Q
\..)
2-26
RELIEF REQUEST O
COMPONENT: Reactor Vessel, Inner and Outer CODE CLASS: 1 Seal Monitoring Tube Penetration Welds EXAMINATION REQUIREMENT:
The reactor vessel, is a Quality Group 1 Component which is part of the pressure-retaining boundary for the Reactor Coolant System. The closure head is sealed to the vessel by two 0-ring seals. The vessel i flange has two penetrations for closure head seal leakage monitoring.
The inner monitoring tube detects leakage across the outer 0-ring seal.
Each of these tubes are connected by a partial penetration weld on the vessel flange gasket seal surface which is weld overlaid with 5/32 in.
thick stainless steel. These welds are outside the pressure boundary for normal operation and will only be pressurized if the closure head seals leak. The monitoring tubes are 1-inch nominal pipe size.
BASIS FOR RELIEF:
Table IWB-2600 Item Bl.5 (vessel penetrations) requires visual examination of these welds during hydrostatic testing. Paragraph IWB-1220 exempts these components based on the size of the tubing, but again imposes a requirement for visual examination during hydrostatic pressure testing. Ultrasonic, surface, or visual examination of the welds cannot be perfomed due to the geometric configuration and inaccessibility due to weld overlap. Hydrostatic pressure testing of the welds is not feasible due to their location outside of the pressure 4
retaining 0-ring seal of the vessel flange. These welds will only be pressurized in the event of loss of integrity of the seals. Failure of both the 0-ring seal and the tube welds is considered unlikely. Loss I of coolant due to complete severance of a monitoring tube can be made.
up by normal charging methods.
O 2-27
. e. -
m.- - - ,- . . - , , , -,. . . ,- r ,- e
! O acute acauesT ALTERNATIVE EXAMINATION:
The welds will not be inspected.
O I
I l
I I
)
O i
2-28
l l
PRESERVICE EKAMINATIONS j OF
' CLASS 2 SYSTEMS AND COMP 0NENTS FOR COMANCHE PEAK NUCLEAR PLANT UNIT #1 1 IWB TABLES 2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
STEAM GENERATOR C1.1 C-A Upper Head to Shell Weld X - -
1 C1.1 C-A Upper Shell to Transition Cone Weld X - -
C1.1 C-A Transition Cone to Lower Shell Weld X - -
iO -
C1.1 C-A Lower Shell to Stub Barrel Weld X -
C1.1 C-A Stub Barrel to Upper Tubesheet Weld X - -
Steam Outlet Nozzle to Head Weld X -
C1.2 C-B C1.2 C-B Feedwater Nozzle to Lower Shell Weld X - -
C1.2 C-B Auxiliary Feedwater Nozzle to Upper Shell X - -
Weld Integrally Welded Supports - 4 -
C1.3 C+C 4
1 4
+
)
3-1
. . . . . . . . . . . . . . _ . _ . . . . . . _ . , , . . . _ . , . _ . .- ~ .. , , _ .__,.._.~ .. _ _ . - . . _ _ _ _
-. - .- ~_. . .. ._ - - _
i i
r IWB TABLES 2600 2500, EXAMINATION ITEM CAT. COPPONENT VOL. SURF. V!S.
C1.4 C-D Pressure Retaining Bolting R R R l LETDOWN HEAT EXCHANGER _
- C1.1 C-A Head to Flange Weld R - -
C1.2 C-B Nozzle to Vessel Head 1 - -
C1.3 C-C Integrally Welded Supports 1 - -
l!
C1.4 C-D Pressure Retaining Bolting 1 - -
I O EXCESS LETDOWN HEAT EXCHANGER
, C1.1 C-A Head to Flange Weld R - -
! C1.2 C-B Nozzle to Vessel Weld 2 - -
C1.3 C-C Integral 1/ Welded Supports 2 - -
C1.4 C-D Pressure Retaining Bolting R R R LETDOWN REHEAT HEAT EXCHANGER C1.1 C-A Head to Shell Weld R - -
C1.1 C-A Shell to Flange Weld R - -
.O C1.2 C-B Nozzle to Vessel Weld '14 - -
3-2
IWB TABLES _
2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
C1.3 C-C Integrally Welded Support - X -
C1.4 C-D Pressure Retaining Bolting 13 - -
VERTICAL RESIDUAL HEAT EXCHANGERS C1.1 C-A Head to Shell Weld R - -
C1.1 C-A Shell to Flange Weld R - -
C1.2 C-B Nozzle to Vessel Welds X - -
C1.3 C-C 7
- '~ ally Welded Supports -
X -
C1.4 C-D Pressure Retaining Bolting R R R REGENERATIVE HEAT EXCHANGER C1.1 C-A Transition Cone to Tubesheet Cire. Welds X - -
C1.1 C-A Head to Shell Welds R - -
C1.1 C-A Shell to tee Cire. Welds R - -
.C1.1 C-A Shell to Tubesheet Welds X - -
C1.1 C-A Tee to Tee Circ. Weld X - -
O C1.2 C-B uozzie to vessei Weid 3 - -
3-3
IWB TABLES 2600 2500 EXAMINATION ITEM CAT. COPP0NENT VOL. SURF. VIS.
C1.3 C-C Integrally Welded Supports 3 - -
C1.4 C-D Pressure Retaining Bolting 3 3 3 SEAL WATER HEAT EXCHANGER C1.1 C-A Head to Shell Weld R - -
C1.1 C-A Shell to Flange Weld R - -
C1.2 C-B Nozzle to Vessel Weld 7 - -
O' C1.3 C-C Integrally Welded Supports 7 - -
C1.4 C-D Pressure Retaining Bolting 7 7 7 VOLUME CONTROL TANS C1.1 C-A Upper Head, to Shell Weld - X - -
C1.1 C-A Shell to Lower Head Weld X - -
C1.2 C-B Nozzle to Vessel Weld 5 5 5 C1.3 C-C Integrally Welded Support - X -
C1.4 C-D Pressure Retaining Bolting 13 13 13 O
REACTOR COOLANT FILTER 3-4
s IWB TABLES 2600 2500 EXAMINATION ITEM CAT. COMPONENT VOL. SURF. VIS.
C1.1 C-A Cover Weldrent to Shell Weld R - -
C1.1 C-A Shell to Lower Head Weld R - -
I C1.2 C-B Nozzle to Vessel Weld '
8 - -
l C1.3 C-C Integrally Welded Supports - X -
l C1.4 C-D Pressure Retaining Bolting 8 8 8 SEAL WATER RETURN FILTER O C1.1 C-^ Cover Weidmeat to Sheii Weid a -
C1.1 C-A Shell to Lower Head Weld R - -
C1.2 C-B Nozzle to Vessel Weld 6 - -
C1.3 C-C Integrally Welded Supports - X -
C1.4 C-D Pressure Retaining Bolting 6 6 6 PIPING C2.1 C-F Circumferential Butt Welds R - -
C2.1 C-G Circumferential Butt Welds R - -
Longitudinal Welds in Fittings
('] C2.2 C-F X - -
3-5
d i
- IWB TABLES i i 1 2600 2500 EXAMINATION I
ITEM CAT. CO WONENT VOL. SURF. VIS.
i j C2.2 C-G Longitudinal Welds in Fittings X - -
)
C2.3 C-F Branch Pipe to Pipe Weld Joints R - -
1 l
j C2.3 C-G Branch Pipe to Pipe Weld Joints R - -
j C2.4 C-D Pressure Retaining Bolting R R R C2.5 C-E-1 Integrally Welded Supports -
X -
C2.6 C-E-2 Support Components - - X i
RESIDUAL HEAT REMOVAL PUMPS i
) C3.1 C-F Pump Casing Welds 9 - -
C3.2 C-D Pressure Retaining Bolting R R R C3.3 C-E-1 Integrally Welded Supports- - X -
C3.4 C-E-2 Support Components - - X CENTRIFUGAL CHARGING PUMPS C3.1 C-F Pump Casing Welds 12 - -
l C3.2 C-D pressure Retaining Bolting R R R C3.3 C-E-1 Integrally Welded Supports - X -
3-6
l l
{
IWB TABLES 2600 2500 EXAMINATION i ITEM CAT. COMPONENT VOL. SURF. VIS.
1 C3.4 C-E-2 Support Components - -
X i
l POSITIVE DISPLACEMENT CHARGING PUMP C3.1 C-F Pump Casing Welds 12 - -
I C3.2 C-D Pressure Retaining Bolting R R R t
l C3.3 C-E-1 Integrally Welded Supports -
X -
i 1
) C3.4 C-E-2 Support Components - - X lO REACTOR COOLANT PUMPS j C3.2 C-D Pressure Rataining Bolting (No. 2 Seal) R R R VALVE C4.1 C-F Valve Body Welds 10 -- -
l C4.1 C-G Valve Body Welds 10 - -
, C4.2 C-D Pressure Retaining Bolting -R R R
) C4.3 C-E-1 Integrally Welded Supports 10 - -
C4.4 C-E-2 Support Components - -
X 3-7 I
! RELIEF REQUEST iO COMPONENT: Stea<n Generator CODE CLASS: 2 Excess Letdown Heat Exchanger f
Vertical Residual Heat Exchanger Piping Residual Heat Removal Pumps f
l Centrifugal Charging Pumps l Positive Displacement Charging Pumps i Reactor Coolant Pumps EXAMINATION REQUIREMENT:
Table IWC-2600 Items C1.4, C2.4 and C3.4 and Table IWC-2520 Category
)
C-D require a visual and either a surface or volumetric examination of l pressure retaining bolting exceeding 1-inch in diameter.
i i
BASIS FOR RELIEF:
I
- The 1977 edition of section XI has revised the requirement for examination of pressure retaining bolting to include only those bolts exceeding 2-inches in diameter. All the above components have pressure retaining bolting less than or equal to 2-inches in diameter.
ALTERNATIVE EXAMINATION:
None i
i
- O 3-8
. . _ - _ _ _ - _ _ _ ._ . . _ - = . .- - -- - _ . . _ - _
(
RELIEF REQUEST O
COMPONENT: Letdown Heat Exchanger CODE CLASS: 2 Excess Letdown Heat Exchanger l
Regenerative Heat Exchanger Vertical Residual Heat Exchangers -
EXAMINATION REQUIREMENT:
l I Tables IWC-2600 Item C1.1 and IWC-2520 category C-A require volumetric examination of pressure vessel head and shell circumferential welds including one plate thickness of base metal on either side of the weld.
BASIS FOR RELIEF:
The geometric configuration of the flange on head to flange welds, prevents volunetric examination from being perfonned on the base metal O on the flange side of the weld to the full extent required by IWC-2520 cateogy C-A.
The design of the support members on the above heat exchangers prevents volunetric examination of the base metal adjacent to the support member to the extent required by IWC-2520 C-A.
ALTERNATIVE EXAMINATION:
100 percent of the weld volume and as much of the tuse metal on either side of the weld as is practical will be volunetrically examined.
l l
A V
3-9
- . _ - -- - . _ _ _ - _ . = . . _ . _ - . - _ _ - . _ _ _ - . _ - - - _ _ - - . .- - - _ - . .
1 l
1
- RELIEF REQUEST ;
J ( f i
- COMPONENT
- Reactor Coolant Filter CODE CLASS: 2 ,
Seal Water Return Filter Seal Water Heat Exchanger Letdown Reheat Heat Exchanger i EXAMINATION REQUIREMENT:
I i
Tables IWC-2600 Item C1.1 and IWC-2520 category C-A require volumetric i
- examination of pressure vessel shell and head circumferential welds including one plate thickness of base metal on either side of the weld.
4 BASIS FOR RELIEF:
1 The thickness of the material utilized for the construction of these i
- components (0.187 inches) is such that meaningful results can not be -
expected with ultrasonic examination.
(])
l 1
ALTERNATIVE EXAMINATION:
These welds will be examined using surface and visual techniques.
O 3-10'
. - . . _ - _ . . , _ _ , _ _ . . - . . _ . _ _ _ ~ . . . , _ . . _ . _ . _ _ . _ _ . _ _ . _ . . . _ _ _ _ _ , _ _ _ _ _ . - . . . . . . .
RELIEF REQUEST COMPONENT: Piping System CODE CLASS: 2 EXAMINATION REQUIREMENT:
Tables IWC-2600 Items C2.1 and C2.3 and IWC-2520 categories C-F and C-G requires volumetric examination of 100 percent of the pressure retain'ng welds in piping which circulates reactor coolant and 50 percent of the pressure retaining welds in piping which do not circulate reactor coolant, including one wall thickness of base metal on either side of the weld.
BASIS FOR RELIEF:
The configuration of the piping system and components are such that limitations may occur for the volumetric examinations of O circumferential butt welds, when the welds occur at geometric discontinuities such as pipe-to-vessel welds, pipe-to-fitting welds and fitting-to-fitting welds. For pipe-to-fitting or pipe-to-vessel nozzle welds, volumetric examinations can be performed to the extent required by T-532 of section V from the weld and pipe surfaces. Volumetric examination from the fitting side will depend on the geonetric configuration. Where elbows and tees are concerned volumetric examination can be performed from the fitting side except when the intrados of the fitting prevents adequate ultrasonic coupling. No volumetric examinations can be performed on the fitting side when the fitting is a valve or a flange. In almost all cases 100 percent of the weld material can be examined. In instances where welds occur at fitting-to-fitting, access restrictions as outlined above occur at both sides of the weld.
O 3-11
RELIEF REQUEST
.'.TERNATIVE EXAMINATION:
Volumetric examination will be performed on 100 percent of the weld volume and on the heat affected zone and base metal to extent practicable. In those instances where ultrasonic examinations cannot be performed on 100 percent of the volume of the weld and heat affected zones, surface examinations will be performed, where possible, to supplement the limited volumetric examination.
l l
O i 3-12
COMANCHE PEAK NUCLEAR PLANT UNIT 1 PRESERVICE EXAMINATIONS CLASS-2 NOTES X - indicates the Code requirement examination which will be conducted R - indicates relief is requested. Reference attached.
Nunbers relate to the tabulations of inspection requirements for the Class 2 components to identify items where the examination requirements of Table IWC-2600 are not applicable. Specific details are:
- 1. The letdown heat exchanger inlet and oulet nozzles are 3 inch nominal diameter, the integrally welded supports are on the shell (Class 3) side of the vessel and tubesheet flange bolting is 1 inch diameter.
- 2. The excess letdown heat exchanger inlet and outlet nozzles are 2 inch nominal diameter and the integrally welded supports are located on the shell (Class 3) side of the vessel.
- 3. The regenerative heat exchanger inlet and outlet nozzles are 3 inch nominal diameter. There are no integrally welded supports on this vessel and no pressure retaining bolting.
- 4. There are no integrally welded supports on the steam generators.
- 5. The volume control tank inlet and outlet nozzles are 4, 3 and 2 inch nominal diameter.
- 6. The seal water return filter inlet and outlet nozzles are 3 inch nominal diameter and pressure retaining bolting is 3/4 inch diameter.
-O 3-13
'J 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.
- 8. The reactor coolant filter inlet and outlet nozzles are 3 inch nominal diameter and cover bolting is 3/4 inch diameter.
- 9. There are no pressure containing welds in the residual heat removal pump casings.
- 10. There are no Class 2 valves with pressure containing welds or integrally welded supports.
- 11. The seal water injection filter is manufactured from w inch nominal diameter pipe.
- 12. There are no pressure retainirig welds in the RHR or charging pump casings.
- 13. There are no components, parts or areas subject to examination that are applicable to this area.
3-14
COMANCHE PEAK NUCLEAR PLANT UNIT #1 PRESERVICE EXAMINATIONS CLASS-3 C0WONENT TYPE OF TEST RELIEF REQUEST Reactor Coolant Piping Visual / Hydrostatic None Hangers Visual None Reactor coolant pump motor Hydrostatic / Visual None oil reservoir cooling coils Chemical & Volume Control System O Piping Visual / Hydrostatic None Hangers Visual None Letdown heat exchanger Visual / Hydrostatic None shell side Mixed-bed Demineralizer Visual / Hydrostatic None Cation-bed Demineralizer Visual / Hydrostatic None-Seal water heat exchanger Visual / Hydrostatic None shell side O
4-1
COMPONENT TYPE OF TEST RELIEF REQUEST l
Boric acid Transfer pump Visual / Hydrostatic None Boric acid Filter Hydrostatic / Visual None l
Boric acid Tanks Visual / Hydrostatic None Moderating Heat Exchanger Visual / Hydrostatic None Tube Side Moderating Heat Exchanger Visual / Hydrostatic None
! Shell Side Letdown Chiller Heat Visual / Hydrostatic None Exchanger Tube Side 1
Letdown Re-heat Heat Visual / Hydrostatic None Exchanger Shell Side Thermal Regeneration Visual / Hydrostatic None Demineralizer Safety Injection System Boron Injection Tank Visual / Hydrostatic None Recirc. Pump Piping Visual / Hydrostatic None Hangers Visual None O
4-2
_- _. _ - - _ . - ~ . ._. _ ._ _. .. _.
! l f
l COMPONENT TYPE OF TEST RELIEF REQUEST
() !
! Boron Injection Surge Visual / Hydrostatic None j Tank 1
i d l Residual Heat Removal System Piping Visual / Hydrostatic None Hangers Visual None i
i Residual Heat Exchanger Visual / Hydrostatic None l
Shell Side 4
! Boron Recycle System i
() Piping Visual / Hydrostatic None Hangers Visual None i
Recycle Evaporator Feed Visual / Hydrostatic None i Pump l
Recycle Evaporator Feed Visual / Hydrostatic None Danineralizer t
Recycle Evaporator Feed Visual / Hydrostatic None i Filter Recycle Hold-up Tank Visual / Hydrostatic None ,
Recycle Evaporator Package Visual / Hydrostatic None
'(:)
i 4 !
.i epwe Ww py,y.,a- gg. y , - - , ,.-,.7..-i.,, -
9y.---.9q 79y,-w _p. --e. > e - wv, 5,,,-,e , ,9,,.-,e.+w., 4- g-
<*Feg-w-gwe-e.-g+gwe,e-c+-.m 9, .yu.. 4g-.e9a.,yy-,...,9m.,g,p9gp,my,,9. w gy 9q..m.p.sg
COMPONENT TYPE OF TEST RELIEF REQUEST (v~')
Distillate Pump Visual / Hydrostatic None Concentrate Pump Visual / Hydrostatic None Containment Spray System Chemical Additive Tank Visual / Hydrostatic None Piping Visual / Hydrostatic None Hangers Visual None Containment Spray Heat Visual / Hydrostatic None Exchanger Shell Side n
U Hydrogen Analyzer System Piping Visual / Hydrostatic None Hangers Visual None Component Cooling Water System Piping Visual / Hydrostatic None Hangers Visual None Heat Exchangers Visual / Hydrostatic None n
4-4
i COMP 0NENT TYPE OF TEST RELIEF REQUEST Pumps Visual / Hydrostatic None i !
Surge Tank Visual / Hydrostatic None l j Pump Strainers Visual / Hydrostatic None
/
Service Water System l
]
J Pumps Visual / Hydrostatic None 4
Piping Visual / Hydrostatic None Hangers Visual None 4
Screen Wash Booster Pumps Visual / Hydrostatic None O
Expansion Joints Visual / Hydrostatic None r
Main Steam Reheat & Steam Dump System Piping Visual / Hydrostatic None Hangers Visual None.
k Auxiliary Feedwater System Piping Visual / Hydrostatic None Hangers Visual None O
4-5
_ COMP 0NENT TYPE OF TEST RELIEF REQUEST Motor Driven Auxiliary Visual / Hydrostatic None Feedwater Puaps Turbine Driven Auxiliary Visual / Hydrostatic None Feedwater Pumps
_D_iesel Oil System Piping Visual / Hydrostatic None Hangers Visual None Diesel Fuel Storage Tank Visual / Hydrostatic None Diesel Fuel Oil Day Tank Visual / Hydrostatic None O
Diescl Fuel Oil Strainer Visual / Hydrostatic None Diesel Generator Start-up Visual /Pneunatic None Air Receiver Spent Fuel Cooling & Clean Up System P~'ing Hydrostatic / Visual None Hangers Visual None Expansion Joints Hydrostatic / Visual None SF Pool Cooling Water Hydrostatic / Visual None O
4-6
(
COMPONENT TYPE OF TEST RELIEF REQUEST O
Pumps SF Pool Heat Exchanger Hydrostatic / Visual None SF Pool Demineralizer Hydrostatic / Visual None Waste Process System ging Hydrostatic / Visual None Hangers Visual None Waste Evaporator Package Visual / Hydrostatic None Gas Compressor Pnetsaatic/ Visual None Gas Decay Tank Pnetsnatic/ Visual None Hydrogen Re, combiner Hydrostatic / Visual None Gas Decay Tank Drain Pump Hydrostatic / Visual None Demineralized & Reactor Make-up Water System Piping Hydrostatic / Visual None Hangers Visual None Reactor Make-up Water Hydrostatic / Visual None Pumps O
4-7
. . - - - - . . - . . - . . - _ _ _ . . _ = - - - _ . - . - - - .__- _ . - - -
i i
i.
1 COMPONENT TYPE OF TEST RELIEF REQUEST j Vents & Drains System Piping Hydrostatic / Visual None -
l Hangers Visual None
> i i Safeguards Bldg. Sump Hydrostatic / Visual None Pumps i
! Ventilation System i
f Piping Hydrostatic / Visual None Hangers Visual None
()
i l Emergency Fan Coi! Units Hydrostatic /Visua i None i
! Chilled Water System i .
Piping Hydrostatic /Vir1al None Hangers Visual None Chillers Hydrostatic / Visual None Surge Tank liydrostatic/ Visual- None Pumps Hydrostatic / Visual None 4-8
Q COMPONENT TYPE OF TEST RELIEF REQUEST Radiation Monitoring System Piping Hydrostatic / Visual None i
! Hangers Visual None l
.I
!1 i
i I
- O l
i l
l I,
lO 1
) 4-9