ML20148T539
| ML20148T539 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/01/1997 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20148T532 | List: |
| References | |
| PROC-970601, NUDOCS 9707090195 | |
| Download: ML20148T539 (76) | |
Text
REVISION 0 June 1,1997 THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PLAN FOR ARKANSAS NUCLEAR ONE UNIT 1 ENTERGY OPERATIONS, INC.
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.b TABLE OF CONTENTS
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SECTION DESCRIPTION PAGE Revision Summary Sheet iii 1.0 Introduction and Plan Description 1-1 1.1 Overview 1-1 i
4 1.2 Basis ofInservice Inspection Plan 1-1 1.3 System Classification 1-3 1.4 Augmented Inservice Inspection Requirements 1-4 2.0 Inservice Inspection Program Drawings 2-1 1
I 2.1 Drawing Nomenclature 2-1 2.2 Piping and Instrumentation Diagrams 2-5 2.3 Piping Isometric Drawings 2-8 i
3.0 Inservice Inspection Piping Line List 3-1 4.0 Inse:Vice Inspection Summary Tables 4-1 4.1 ASME Section XI Inservice Inspections 4-1 5.0 Alternative Requirements to ASME Section XI 5-1 5.1 Adoption ofCode Cases 5-1 5.2 Use of Subsequent Editions of ASME Section XI 5-4 5.3 Inservice Inspection Request for Alternative and 5-5 ReliefRequest Index 1
l 5.4 Inservice Inspection Requests for Alternatives and 5-5 ReliefRequests f
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l REVISION
SUMMARY
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l SECTION EFFECTIVE PAGE(S)
REVISION DATE 1.0 1-1 0
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6/1/97 2.1 2-1 to 2-5 0
6/1/97 2.2 2-5 to 2-7 0
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6/1/97 4.0 4-1 0
6/1/97 4.1 4-1 to 4-10 0
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6/1/97 5.1 5-1 to 5-4 0
6/1/97 5.2 5-4 0
6/1/97 5.3 5-5 0
6/1/97 5.4 Reference Section 5.3 for Revision Status of Requests for Alternatives and ReliefRequests l
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ANO Unit I 3'd Interval Inservice Inspection Plan
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I SECTION 1.0 l
INTRODUCTION AND PLAN DESCRIPTION l
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1.1.1 This Inservice Inspection Plan outlines the requirements for the inspection of Class l
1,2, and 3 pressure retaining components and their suppons at Arkansas Nuclear One, Unit 1 (ANO-1).-
1.1.2 This Inservice Inspection Plan will be effective from June 1,1997, through and l
l including May 31, 2007, which represents the third ten-year interval for ANO-1.
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1.1.3 The key features of this Plan are the Introduction and Plan Description, List of Applicable Drawings, Piping Line List, Summary Tables, and Requests for j
Alternatives. The details of the Inservice Inspection Program referenced in this Inservice Inspection Plan are contained in documents that are available at ANO.
l These documents include, but are not limited to, piping and instrument diagrams, l
piping isometric drawings, a database listing of each weld, valve, support, etc. in the Inservice Inspection Program and documents supporting implementation of the InserviceInspection Program.
I 1.2 Basis ofInserviceInspection Plan l
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1.2.1 This Inservice Inspection Plan was developed in accordance with the requirements
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delineated in the August 8,1996, issue of 10CFR50.55a. As such, Entergy i
operations will implerrent the augmented reactor pressure vessel examination requirements of 10CFR50.55a(g)(6)(ii)(A).
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1.2.2 This Inservice Inspection Plan was developed in accordance with the 1992 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure ~
Vessel Code,Section XI, Subsections IWA, IWB, IWC, IWD, and IWF, for Inspection Program B. In addition, the following portions of the ASME Section XI 1993 Addenda has been adopted in lieu of the corresponding portions of the 1992 Edition.
1.2.2.1 General pressure test requirements ofIWA-5000 consisting of Table IWA-5210-1, paragraph IWA-5250(a)(2) and paragraph IWA-5265(b).
1.2.2.2 Class 1 pressure test requirements consisting of Table IWB-2500-1, Examination Categories B-E and B-P, and Article IWB-5000 in its entirety.
p 1.2.2.3 Class 2 pressure test requirements consisting of Table IWC-2500-1, Examination Category C-H, and Article IWC-5000 in its entirety.
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1.2.2.4 Class 3 pressure test requirements consisting of Article IWD-5000 in its entirety.
Accordingly, this Inservice Inspection Plan provides the details necessary for performing the inservice inspection of the ANO-1 Class I, 2, and 3 pressure retaining components and supports.
1.2.3 Use of the 1992 Edition of ASME Section XI with the portions of the 1993 Addenda referenced in 1.2.2 was authorized by the Nuclear Regulatory Commission in a letter dated December 12,1996 (0CNA129613), entitled:
" Evaluation of Entergy Operations, Inc., Request for Authorization to Update Inservice Inspection Programs to the 1992 and Portions of the 1993 ASME Boiler and Pressure Vessel Code,Section XI for Arkansas Nuclear One, Units 1 and 2, Grand Gulf Nuclear Station, River Bend Station, and Waterford Steam Electric Station, Unit 3 (TAC Nos. M94472, M94471, M94454, M94473, and M94488)."
This letter also approved the extension of the second interval at ANO-1 and addressed the implementation of ASME Section XI Subsections IWE and IWL. In addition, the letter stated that the Nuclear Regulatory Commission had not completed their review of Entergy Operations' request to implement alternative criteria to ASME Section XI, Appendix VIII. Until such time that the review is completed, Entergy Operations will continue to use the current examination criteria including Appendix VII of ASME Section XI,1992 Edition, and Regulatory Guide 1.150 at ANO-1.
1.2.4 The following ASME Section XI,1992 Edition Subsections, Articles, or Paragraphs are not included or addressed in this Inservice Inspection Plan.
1.2.4.1 The containment liner and concrete inspection and testing requirements of Subsections IWE and IWL, are not included in this Inservice Inspection Plan. The rules of Subsections IWE and IWL as invoked by 10CFR50 will be implemented in a separate submittal to the NRC.
1.2.4.2 The pump and valve testing requirements of Subsections IWP and IWV are not included in this Inservice Inspection Plan. The rules ofIWP and IWV will be addressed in a separate submittal to the NRC after completion of the current inservice testing interval on December 15, 1997.
1.2.4.3 The snubber inservice inspection requirements of Article IWF-5000 are I
not addressed in this Inservice Inspection Plan. The extent, frequency, j
and acceptance standards for snubber assembly testing and inspection will be in accordance with ANO-1 Technical Specification 4.16.
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ANO Unit 13'd Interval Inservice Inspection Plan 1.2.4.4 The steam generator tubing examination requirements of Table IWB-2500-1, Examination Category B-Q are not addressed in this Inservice Inspection Plan. As allowed by AShE Section XI, IWB-2413, the extent, frequency, and acceptance standards for steam generator tubing inspection and testing will be in accordance with ANO-1 Technical Specification 4.18.
1.2.5 Alternative requirements to AShE Section XI are set forth in Section 5.0 of this Inservice Inspection Plan.
Alternative requirements are in accordance with 10CFR50.55a and AShE Section XI.
1.2.6 With the exception of examinations that may be deferred until the end of the inspection interval as specified in Table IWB-2500-1, inservice inspections shall be performed in accordance with Inspection Program B as outlined in IWA-2432, IWB-2412, IWC-2412 and IWD-2412 of AShE Section XI. The inspection schedule for the third interval is divided into three periods such that approximately one third of the inspections will be completed every period. Successive inspections shall be in accordance with IWB-2420, IWC-2420, IWD-2420 and IWF-2420.
Deviations to inspection schedules may occur provided compliance with Code requirements is maintained.
1.2.7 The commercial operating license date for ANO-1 was December 19,1974. The second inspection interval was extended from December 19,1994 to December 1, 1996, es allowed by a Nuclear Regulatory Commission letter dated August 2,1994 (ICNA089402), emitted, " Interim Extension of 120-Month Interval for Inservice Inspection and Inservice Testing (ISI/ IST) Programs for Arkansas Nuclear One, Unit 1 (TAC No. M89337)." The second interval was further extended to June 1, 1997, by the Nuclear Regulatory Commission letter referenced in paragraph 1.2.3 of this Inservice Inspection Plan.
1.3 System Classifications 1.3.1 At the time ANO-1 was constructed, the AShE Boiler and Pressure Vessel Code only addressed nuclear vessels and associated piping up to and including the first isolation valve.
Therefore, the piping codes of record were USAS B31.7, February 1968 Draft with June 1968 Errata for nuclear piping, and USAS B31.1.0
- 1967 Edition for non-nuclear piping.
Consequently, ANO-1 piping is not designated by ASME Section III Code Class 1,2 and 3 systems.
1.3.2 The quality group clasrification system for water, steam, and radioactive waste containing components important to the safety of water-cooled nuclear power plants 's established by NRC Regulatory Guide 1.26, Revision 3, in conjunction with 10CFR50.55a. Regulatory Guide 1.26, " Quality Group Classification and Standards," defines the Quality Group Classification System consisting of four Quality Groups, A through D. The definition of Quality Group A is provided by 1-3 Resision 0
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ANO Unit 13 Interval Inservice Inspection Plan 10CFR50.2 under " Reactor Coolant Pressure Boundary." The definitions of Groups B, C, and D (Class 2, Class 3 and ISI non-classed, respectively) are i
provided by Regulatory Guide 1.26.
1.3.3 Piping and components subject to inservice inspection are shown on the Piping and Instrumentation Diagrams listed in Section 2.2 of this Inservice Inspection Plan.
i Specific piping lines subject to inservice inspection are documented in the Piping Line List contained in Section 3.0 of this Inservice Inspection Plan. Pursuant to 1
10CFR50.55a, the inservice inspection requirements of ASME Section XI have
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been assigned to these piping lines and components within the constraints of existing plant design. Applicable piping, components and supports have been classified as exempt from examination requirements as defined in ASME Section i
XI, paragraphs IWB-1220, IWC-1220, IWD-1220 and IWF-1230.
1.4 Augmented Inservice Inspection Reauirements Augmented inservice inspection requirements are those examinations that are specified by documents other than the ASME Section XI Code.
Frequently, these augmented examinations are at the request of the Nuclear Regulatory Commission through such mechanisms as Bulletins, Notices, and Regulatory Guides.
However, the Inservice Inspection Program also addresses several plant specific, internal commitments. In some instances, these augmented examinations may include piping and components outside the inservice inspection boundaries. The augmented examinations addressed by the ANO-1 Inservice Inspection Program are as follows-1.4.1 Ultrasonic examinations on the reactor pressure vessel shall be conducted in accordance with U.S. Nuclear Regulatory Commission Regulatory Guide 1.150, Rev.1, " Ultrasonic Testing of Reactor Vessel Welds During Preservice and j
Inservice Examinations."
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1.4.2 High Energy Line Break (HELB) and Moderate Energy Line Break (hELB) examinations shall be performed in accordance 'th Upper Level Document ULD-0-TOP-07, "HELB/ MELB Topical ULD," Calculation 86D-1005-29, Appendix B, and ANO-1 Technical Specification 4.15.
1.4.3 Visual inspections shall be performed on High Pressure Injection (HPI) support MU-167 and associated piping in accordance with ANO Condition Report CR-1-96-0502.
1.4.4 The examination of stagnant, borated water systems (i.e., Nuclear Regulatory Commission IE Bulletin 79-17) is addressed in Request Number 97-003.
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Inservice Inspection Plan 1.4.5 Enhanced ultrasonic examinations shall be performed on 17 HPI welds and visual inspection shall be performed on two segments of HPI piping in acccrdance with Entergy Operations' Janua y 31, 1991, response to Nuclear Regulatory Commission IE Bulletin 88-08 (0CAN019102).
l 1.4.6 Surface and volumetric examinations of reactor coolant pump flywheels shall be conducted in accordance with ANO-1 Technical Specification 4.2.6.
1.4.7 Ultrasonic examinations on one pressurizer upper level tap shall be conducted in accordance with ANO Calculation 86E-0074-103, memorandum ANO-92-00507, and the NRC submittal dated August 5,1993 (ICAN089302).
1.4.8 Ultrasonic examinations shall be performed on reactor coolant pump shafts and surface examinations shall be performed on reactor coolant pump shaft covers each time a pump is disassembled in accordance with Plant Impact Evaluation (PIE) 87-0082B aad Byron Jackson Technical Service Bulletin 8710-80-009.
1.4.9 Surface examinations and visual inspections shall be performed on emergency feedwater riser welds in accordance with Babcock & Wilcox letter No.
APL-85-349, " Water Hammer Concern in Auxiliary Feedwater Headers."
1.4.10 Visual VT-2 inspections shall be performed on pressurizer level taps in accordance with ANO Condition Report CR-1-90-0853-07 and memorandum No.
1.4.11 Surface examinations and VT-3 visual inspections shall be performed on special lifting devices in accordance with Entergy Operations
- June 8,1984, response to NUREG-0612, " Control of Heavy Loads at Nuclear Power Plants."
(0CAN068402) 1.4.12 Ultrasonic examinations shall be performed on HPI nozzle knuckles and radiography shall be performed on HPI nozzle thermal sleeves in accordance with ANO Condition Reports CR-1-89-0335 and CR-1-89-0508 and Entergy Operations
- submittal to the NRC dated April 22,1985 (1CAN048501).
1.4.13 Ultrasonic examinations and thickness measurements shall be performed on four main steam moisture and reheater piping welds in accordance with ANO Condition Report CR-1-89-0621.
1.4.14 Visual inspections shall be performed on VSC-24 dry spent fuel storage casks per 1.3.2 and 1.3.3 of the storage cask's " Certificate of Compliance" which was issued in accordance with 10CFR72.
I 1.4.15 Visual inspections shall be performed on reactor coolant pump seal injection piping l
and supports in accordance with ANO Condition Report CR-1-90-0514-11.
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d ANO Unit 13 Interval Inservice Inspection Plan 1.4.16 Ultrasonic examinations shall be performed on pressurizer relief valve piping in accordance with ANO Condition Reports CR-1-92-0244 and CR-1-91-0131, I
Item 8.
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1.4.17 Ultrasonic examinations shall be performed on the pressurizer surge line elbow as
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discussed in Nuclear Regulatory Commission letter No. ICNA029402 (TAC No.
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M72108) dated February 24,1994.
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Inservice Inspection Plan SECTION 2.0 INSERVICE INSPECTION PROGRAM DRAWINGS This section provides a listing of the vario2s drawings applicable to the ANO-1 Inservice l
Inspection Program.
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2.1 Drawing Nomenclature 2.1.1 Zone Designators l
Table 2.1 below lists the System Zone Designations used for the piping systems and components subject to inservice inspection at ANO-1.
TABLE 2.1 SYSTEM ZONE DESIGNATORS ZONE SYSTEM DESIGNATOR 001 REACTOR PRESSURE VESSEL 002 REACTOR PRESSURE VESSEL HEAD i
AND CONTROL ROD DRIVES 003 STEAM GENERATOR E24A 004 STEAM GENERATOR E24B l
005 PRESSURIZER 006 STEAM GENERATOR"K' TO PUMP 1 Al (RCP-C) 007 RCP-C TO REACTOR VESSEL 008 STEAM GENERATOR"A" TO PUMP 1A2 (RCP-D) 009 RCP-D TO REACTOR VESSEL 010 STEAM GENERATOR"B" TO PUMP IBl (RCP-A) 011 RCP-A TO REACTOR VESSEL 012 STEAM GENERATOR "B" TO PUMP IB2 (RCP-B) 013 RCP-B TO REACTOR VESSEL 2-1 Revision 0
ANO Unit 13'd Interval Inservice Inspection Plan TABLE 2.1 SYSTEM ZONE DESIGNATORS (con't)
ZONE SYSTEM DESIGNATOR i
014 REACTOR COOLANT SYSTEM -HOT LEG FROM REACTOR VESSEL TO STEAM GENERATOR"A" 1
015 REACTOR COOLANT SYSTEM - HOT LEG FROM REACTOR VESSEL TO STEAM GENERATOR "B" 016 PRESSURIZER SURGE j
017 DECAY HEAT REMOVAL i
018 PRESSURIZER AUXILIARY SPRAY 2
019 CORE FLOOD 020 HIGH PRESSUREINJECTION TO Al LOOP (P32C)
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021 HIGH PRESSURE INJECTION TO A2 LOOP (P32D) 022 HIGH PRESSUREINJECTION TO B1 LOOP (P32A) 023 HIGH PRESSUREINJECTION TO B2 LOOP (P32B) 024 LETDOWN COOLER AND DRAIN 025 REACTOR COOLANT SYSTEM DRAINS 026 MAIN FEEDWATER 027 MAIN FEEDWATER 028 MAIN STEAM 029 MAIN STEAM 030 MAIN STEAM 031 MAIN STEAM 032 MAKE-UP PUMP SUCTION i
033 DECAY HEAT REMOVAL TO PUMPS 034 LOW PRESSURE INJECTION - PUMP "A" DISCHARGE TO PENETRATION 2-2 Revision 0
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ANO Unit 13 Interval Inservice Inspection Plan l:
i TABLE 2.1 -
I SYSTEM ZONE DESIGNATORS (con't) l i
ZONE SYSTEM i
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035 LOW PRESSURE INJECTION - PUMP "B" DISCHARGE TO PENETRATION l
036 LOW PRESSURE INJECTION I
PENETRATIONS TO CORE FLOOD 037 LETDOWN COOLER E29A L
038 LETDOWN COOLERE29B i
039 EMERGENCY FEEDWATER 040 EMERGENCY FEEDWATER 041 DECAY HEAT REMOVAL COOLER E35A 042 DECAY HEAT REMOVAL COOLERE35B 043 REACTOR COOLANT PUMP "A" AND MOTOR FLYWHEEL 1 A2 l
044 REACTOR COOLANT PUMP "B" AND l
MOTOR FLYWHEEL 1B2 045 REACTOR COOLANT PUMP "C" AND j
MOTOR FLYWHEEL IBl 046 REACTOR COOLANT PUMP "D" AND MOTOR FLYWHEEL 1Al l
047 PRESSURIZER RELIEF 048 PRESSURIZER RELIEF 049 SEPSICE WATER AND EMERGENCY FEEDWATER 050 SERVICE WATER 051 SERVICE WATER 052 SERVICE WATER 053 SERVICE WATER 054 SERVICE WATER 055 BUILDING SPRAY"A" l
056 BUILDING SPRAY"B" 2-3 Revision 0
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l Inservice Inspection Plan TABLE 2.1 SYSTEM ZONE DESIGNATORS (con't)
ZONE SYSTEM DESIGNATOR 057 EhERGENCY FEEDWATER 063 BUILDING SPRAY"A" AND"B"INSIDE REACTOR BUILDING 070 PRESSURIZER SAFETY VALVE
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DISCHARGE 1
071 BORATED WATER STORAGE TANK ATTACHED PIPING l
100 AUGMENTED INSPECTIONS 2.1.2 Piping Classifications 2.1.2.1 Piping classifications are designated by a three-letter code. Listed below are the appropriate letter designations for piping at ANO-1. The first letter indicates the Standard Rating Class; the second letter the type of material; and the third letter the Code to which the piping is designed.
2.1.2.2 First Letter-Pressure Rating Class 1
B - Class 2500 C - Class 1500 D - Class 900 E - Class 600 l
F - Class 400 G - Class 300 H - Class 150 J - For general use as designated on piping class sheets K - For general use as designated on piping class sheets L - For general use as designated on piping class sheets M - For general use as designated on piping class sheets V - Vendor supplied; installed by Bechtel 1
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Eecond Letter-Material B - Carbon Steel C - Stainless Steel D - Copper E - For general use as designated on piping class sheets F - For general use as designated on piping class sheets G - For general use as designated on piping class sheets Third Letter-Design Codes A - Nuclear Power Piping, ANSI B31.7, Class I i
B - Nuclear Power Piping, ANSI B31.7, Class II C - Nuclear Power Piping, ANSI B31.7, Class III-D - Code for Pres.cre Piping, ANSI B31.1.0 2.1.3 Line Identification Numbers The line numbers identified on the drawings listed herein provide useful information about the piping.
The lines are identified using the following j
convention:
EBB 10" Pipe Classification l
l Sequence Number Pipe Size 1
Each line, or portion ofline, is assigned a pipe classification, line sequence number, and pipe size. The line identification numbers can be cross referenced to the i
l Piping Line List provided in Section 3.0 of this ISI Plan to determine the line l
l description, system, Piping and Instrumentation Diagram (P&ID), and normal operating temperature and pressure.
The pipe classification can be cross referenced to ANO Specification ANO-M-555 to determine the pipe schedule and material specification.
2.2 Piping and Instnimentation Dinerams l
Table 2.2 provides a listing of the P& ids that depict the piping subject to inservice inspection at ANO-1.
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ANO Unit 13 Interval Inservice Inspection Plan TABLE 2.2 PIPING AND INSTRUMENTATION DIAGRAMS DRAWING SHEET TITLE NUMBER NUMBER M'-200 1
INSTRUMENTATION AND COMPONENT SYMBOLS M-200 2
INSTRUMENTATION AND COMPONENT SYMBOLS M-200 3
INSTRUMENTATION AND COMPONENT SYMBOLS M-201 1
INSTRUMENTATION SYMBOLS M-204 3
EMERGENCY FEEDWATER M-204 5
EMERGENCY FEEDWATER STORAGE M-204 6
EMERGENCY FEEDWATER PUMP TURBINE M-206 1
STEAM GENERATOR SECONDARY SYSTEM M-206 2
MSIV OPERATOR CONTROLS M-209 1
CIRCULATING WATER, SERVICE WATER & FIRE WATERINTAKE STRUCTURE EQUIPMENT M-209 2
CONDENSER VACUUM, CIRCULATING WATER &
DISCHARGE STRUCTURE EQUIPMENT M-210 1
SERVICE WATER M-212 2
DEMIN. WATER DISTRIBUTION M-213 1
DIRTY RADIOACTIVE WASTE DRAINAGE &
FILTRATION M-213 2
LAUNDRY WASTE AND CONTAINMENT &
AUXILIARY BUILDING SUMP DRAINAGE M-214 1
CLEAN LIQUID RADIOACTIVE WASTE M-214 2
CLEAN LIQUID RADIOACTIVE WASTE M-214 3
CLEAN LIQUID RADIOACTIVE WASTE M-215 1
GASEOUS RADIOACTIVE WASTE M-219 1
FIRE WATER M-221 2
EhERGENCY CHILLED WATER SYSTEM AUXILIARY BUILDING ELECTRICAL ROOMS M-222 1
CHILLED WATER SYSTEM REACTOR AND AUXILIARY BUILDINGS M-230 1
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l TABLE 2.2 PIPING AND INSTRUMENTATION DIAGRAMS (con't) 6 DRAWING SHEET TITLE NUMBER NUMBER g
l M-230 2
REACTOR COOLANT SYSTEM M-231 1
MAKEUP & PURIFICATION SYSTEM M-231 2
MAKEUP & PURIFICATION SYSTEM M-231 3
MAKEUP & PURIFICATION SYSTEM l
M-232 1
DECAY HEAT REMOVAL SYSTEM M-233 1
CHEMICAL ADDITION SYSTEM M-234 1
INTERMEDIATE COOLING SYSTEM M-234 2
INTERhEDIATE COOLING SYSTEM M-235 1
SPENT FUEL COOLING SYSTEM M-236 1
REACTOR BUILDING SPRAY & CORE FLOODING SYSTEMS M-237 1
SAMPLING SYSTEM j
M-237 4
POST ACCIDENT CONTAINMENT ATMOSPIERE SAMPLING SYSTEM M-238 1
CONTROL ROD DRIVES & MISCELLANEOUS i
REACTOR COOLANT PUMP CONNECTIONS M-238 2
REACTOR COOLANT PUMP P-32B AND MISCELLANEOUS CONNECTIONS M-261 1
REACTOR BUILDING HVAC M-264 1
VENTILATION SYSTEM AIR FLOW CONTAINhENT PENETRATION ROOM l
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2.3 '
Pinina Isometric Drawines l
l Table 2.3 provides a listing of the Piping Isometric Drawings for systems subject to inservice inspection. These drawings identify piping welds, flanges, valves, pumps, and piping supports that are within the non-exempt piping boundaries. In addition, system identifications, pipe classifications,- pipe sizes, containment penetrations, and piping configurations are identified. Piping and components that are exempt from nondestructive and visual examination in accordance with ASME Section XI, paragraphs IWB-1220, IWC-1220, and IWD-1220 :nay also be depicted on these drawings.
TABLE 2.3
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PIPINGISOMETRIC DRAWINGS DRAWING TITLE NUMBER 1-MS-I LARGE PIPEISOhETRIC MAIN STEAM FROM STEAM GENERATOR E-24A 1-MS-2 LARGE PIPE ISOMETRIC MAIN ' TEAM FROM STEAM GENERATOR E-24A 1-MS-3 LARGE PTPEISOMETRIC MAIN STEAM FROM STEAM GENERATOR E-24B l-MS-4 LARGE PIPE ISOMETRIC STEAM GENERATOR E-24B SECONDARY LINE FROM CONTAINMENT TO CV-2692 1-MS-5 LARGE PIPE ISOMETRIC (Sheet 1)
MAIN STEAM TO ISOLATION VALVES UPSTREAM OF EMERGENCY FEEDWATER PUMP TURBINE K-3 l-MS-5 LARGE PIPE ISOMETRIC i
(Sheet 2)
MAIN STEAM LINE ATMOSPHERIC DUMP (CV-2668) l-MS-101 LARGE PIPEISOhETRIC MAIN STEAM HEADER j
1-MS-103 LARGE PIPEISOMETRIC 4
MAIN STEAM HEADER 1-MS-118 LARGE PIPEISOMETRIC (Sheet 1)
STEAM ADMISSION SYSTEM TO EMERGENCY FEEDWATER TURBINE (K-3) 1-MS-Il8 LARGE PIPE ISOMETRIC (Sheet 2)
STEAM ADMISSION TO EMERGENCY FEEDWATER TURBINE (K-3) 2-MFW-1 LARGE PIPE ISOMETRIC MAIN FEEDWATER TO STEAM GENERATOR E-24B 2-8 Revision 0
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l TABLE 2.3 l
PIPING ISOMETRIC DRAWINGS (con't) l DRAWING TITLE NUMBER 2-MFW-2 LARGE PIPE ISOhETRIC L
MAIN FEEDWATER l
2-MFW-110 LARGE PIPEISOMETRIC l
MAIN FEEDWATER 3-EFW-107 LARGE PIPE ISOhETRIC EhERGENCY FEEDWATER 3-EFW-108 EhE!1GENCY FEEDWATER (Sheets 1 and 2)
SYSTEM PIPINGISOhETRIC 3-EFW-109 LARGE PIPE ISOMETRIC EMERGENCY DISCHARGE FEEDWATER PUMP P-7A TO ISOLATION VALVE 3-EFW-110 EhERGENCY FEEDWATER (Sheet 1)
SYSTEM PIPING ISOMETRIC 3-EFW-110 LARGE PIPEISOMETRIC (Sheet 2)
EhERGENCY FEEDWATER FROM P-7B TO CV-2626 3-EFW-111 LARGE PIPEISOMETRIC EMERGENCY FEEDWATER FROM P-7B TO CV-2670 3-EFW-112 EMERGENCY FEEDWATER SYSTEM PIPING ISOMETRIC 3-EFW-113 LARGE PIPE ISOhETRIC (Sheets 1 and 2)
EhERGENCY FEEDWATER PUMP P-7A & P-7B INLET PIPING j
3-EFW-114 LARGE PIPEISOMETRIC (Sheets 1,2 and 3)
EhERGENCY FEEDWATER PUMP INLET HEADER PIPING l
(S ee 1)
ERG C
E \\A R PUMP P-7B PIPING TO CV-2670 3-EFW-115 EMERGENCY FEEDWATER (Sheet 2)
SYSTEM PIPING ISOMETRIC 3-EFW-116 EMERGENCY FEEDWATER (Sheets 1,2 and 3)
SYSTEM PIPING ISOMETRIC 3-EFW-117 EMERGENCY FEEDWATER SYSTEM PIPING ISOhETRIC 3-EFW-118 EhERGENCY FEEDWATER l
SYSTEM PIPING ISOhETRIC l
3-EFW-119 EhERGENCY FEEDWATER SYSTEM PIPING ISOhETRIC j
5-BS-1 LARGE PIPE ISOhETRIC REACTOR BUILDING SPRAY 2-9 Revision 0
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Inservice Inspection Plan l
l TABLE 2.3 PIPING ISOMETRIC DRAWINGS (cen't) l DRAWING TITLE NUMBER l
5-BS-2 LARGE PIPE ISOMETRIC SPRAY PUMP DISCHARGE 5-BS-3 LARGE PIPE ISOMETRIC SPRAY PUMP DISCHARGE TO BORATED WATER STORAGE TANK 5-BS-4 LARGE PIPE ISOMETRIC P-35A DISCHARGE TO CONTAINhENT AND RETURN TO BWST 5-BS-5 LARGE PIPE ISOMETRIC REACTOR BUILDING SPRAY 5-BS-6 LARGE PIPEISOMETRIC SPRAY PUMP SUCTION 5-BS-7 LARGE PIPEISOMETRIC SPRAY PUMP SUCTION 5-BS-101 LARGE PIPE ISOhETRIC REACTOR BUILDING SPRAY SYSTEM 5-BS-102 LARGE PIPE ISONETRIC REACTOR BUILDING SPRAY SYSTEM 5-BS-103 LARGE PIPE ISOMETRIC REACTOR BUILDING SPRAY 5-BS-109 LARGE PIPE ISOMETRIC REACTOR BUILDING SPRAY 6-CF-1 LARGE PIPEISOhETRIC
)
CORE FLOODING TO REACTOR 6-CF-2 LARGE PIPEISOhETRIC CORE FLOODING TO REACTOR 7-DH-1 LARGE PIPE ISOhETRIC DECAY HEAT REMOVAL TO REACTOR 7-DH-2 LARGE PIPE ISOhETRIC DECAY HEAT PUMP DISCHARGE TO REACTOR 7-DH-3 LARGE PIPE ISOMETRIC i
DECAY HEAT REMOVAL FROM REACTOR 7-DH-4 LARGE PIPE ISOhETRIC DECAY HEAT REMOVAL FROM REACTOR 7-DH-5 LARGE PIPE ISOMETRIC DECAY HEAT PUMP DISCHARGE 7-DH-6 LARGE PIPE ISOMETRIC DECAY HEAT PUMP DISCHARGE 2 - 10 Revision 0
l d
ANO Unit 13 Interval Inservice Inspection Plan TABLE 2.3 PIPING ISOMETRIC DRAWINGS (con't)
DRAWING TITLE NUMBER l
7-DH-8 LARGE PIPE ISOMETRIC DECAYHEAT PUMP DISCHARGE 7-DH-9 LARGE PIPEISOMETRIC DECAY HEAT REMOVAL 7-DH-10 LARGE PIPEISOMETRIC DECAY HEAT PUMP DISCHARGE 7-DH-11 LARGE PIPEISOMETRIC DECAY HEAT PUMP DISCHARGE q
7-DH-12 LARGE PIPEISOMETRIC l
(Sheets I and 2)
ENGINEERED SAFEGUARDS PUMP SUCTION HEADER 7-DH-13 LARGE PIPEISOMETRIC DECAY HEAT PUMP SUCTION HEADER 7-DH-14 LARGE PIPEISOMETRIC PRIMARY MAKE UP PUMP SUCTION HEADER 7-DH-15 LARGE PIPEISOMETRIC MAKE-UP PUMP SUCTION 7-DH-16 LARGE PIPE ISOMETRIC DECAY HEAT PUMP SUCTION FROM REACTOR BUILDING SUMP 7-DH-17 LARGE PIPE ISOMETRIC DECAYMdAT PUMP SUCTION FROM REACTOR BUILDING SUMP 7-DH-22 LARGE PIPEISOMETRIC BORATED WATER STORAGE TANK PURIFICATION 7-DH-22A LARGE PIPEISOMETRIC DECAY HEAT REMOVAL TO REACTOR 7-DH-23 LARGEPIPEISOMETRIC i
DECAY HEAT REMOVAL TO REACTOR 7-DH-102 LARGE PIPEISOMETRIC BORATED WATER STORAGE TANK PIPING 7-DH-103 LARGE PIPEISOMETRIC BORATED WATER STORAGE TANK PIPING 12-CON-141 LARGE PIPE ISOMETRIC EMERGENCY FEEDWATER FROM T-41B TO EFW PUMPS P-7A AND P-7B 12-CON-142 LARGE PIPE ISOMETRIC EMERGENCY FEEDWATER FROM T-41B TO EFW PUh@S P-7A AND P-7B j
2-11 Revision 0
ANO Unit 13' m wal Inservice Inspectior, Plan t
l TABLE 2.3 PIPING ISOMETRIC DRAWINGS (con't) i DRAWING TITLE NUMBER 12-CON-143 LARGE PIPE ISOMETRIC EMERGENCY FEEDWATER FROM T-41B TO EFW PUMPS l
P-7A AND P-7B l
12-CON-144 LARGE PIPE ISOhETRIC EhERGENCY FEEDWATER PIPING FROM T-4IB TO EFW PUMPS P-7A AND P-7B 12-CON-147 EhERGENCY FEEDWATER RECIRCULATION TO T41B 13-SW-1 LARGE PIPE ISOMETRIC SERVICE WATER PENETRATION PIPING TO VCC 2C & 2D 13-SW-2 SERVICE WATER FROM VCC 2C & 2D 13-SW-3 LARGE PIPE ISOMETRIC SERVICE WATER PENETRATION PIPING 13-SW-4 LARGE PIPE ISOhETRIC SERVICE WATER PENETRATION PIPING 13-SW-101 LARGE PIPEISOhETRIC SERVICE WATER (ESSENTIAL) 13-SW-102 LARGE PIPE ISOMETRIC SERVICE WATER (ESSENTIAL) 13-SW-103 LARGE PIPEISOhETRIC SERVICE WATER SUPPLY TO VCC 2A & VCC 2B 13-SW-104 LARGE PIPEISOhETRIC SERVICE WATER ESSENTIAL RETURN 13-SW-105 LARGE PIPEISOMETRIC SERVICE WATER VCC 2A & 2B RETURN 13-SW-106 LARGE PIPE ISOMETRIC SERVICE WATER SUPPLY LOOP I 13-SW-108 LARGE PIPEISOhETRIC SERVICE WATER SUPPLY TO COOLER E-35A 13-SW-110 LARGE PIPE ISOhETRIC SERVICE WATER SUPPLY 13-SW-111 LARGE PIPEISOhETRIC SERVICE WATER RETURN FROM EhERGENCY DIESEL GENERATOR JACKET COOLERS l
13-SW-112 LARGE PIPINGISOMETRIC SERVICE WATER RETURN l
13-SW-113 LARGE PIPEISOhETRIC j
E-35A RETURN l
2 - 12 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 2.3 i
PIPING ISOMETRIC DRAWINGS (con't)
)
DRAWING TITLE NUMBER 13-SW-114 LARGE PIPEISOMETRIC SERVICE WATER SUPPLY TO EMERGENCY POND j
13-SW-115 LARGE PIPE ISOhETRIC
]
SERVICE WATER RETURN 13-SW-116 LARGE PIPE ISOhETRIC SERVICE WATER RETURN' FROM DECAY HEAT EXCHANGER E-35B 13-SW-118 LARGE PIPE ISOMETRIC SERVICE WATER SUPPLY TO DECAY HEAT EXCIMNGER E-35B 13-SW-119 LARGE PIPE !SOMETRIC SERVICE WATER SUPPLY l
13-SW-120 LARGE PIPE ISOMETRIC SERVICE WATER RETURN 13-SW-122 LARGE PIPE ISOhETRIC 1
SERVICE WATER TO EMERGENCY FEEDWATER SUCTION 13-SW-126 LARGE PIPE ISOhETRIC SERVICE WATER SUPPLY ESSENTIAL 13-SW-128 SERVICE WATER FROM VCC 2C & D 13-SW-129 SERVICE WATER FROM VCC 2A & B 13-SW-130 SERVICE WATER SUPPLY TO VCC 2A & B 13-SW-131 SERVICE WATER SUPPLY TO VCC 2C & D i
13-SW-132 SERVICE WATER SUPPLY 13-SW-133 LARGE PIPE ISOhETRIC SERVICE WATER PUMP TO DISCHARGE 13-SW-134 LARGE PIPE ISOMETRIC SERVICE WATER ESSENTIAL
{
13-SW-135 LARGE PIPE ISOhETRIC SERVICE WATER SUPPLY TO VCC 2D 13-SW-136 LARGE PIPE ISOMETRIC SERVICE WATER SUPPLY TO VCC 2A 13-SW-137 LARGE PIPE ISOhE1RIC SERVICE WATER RETURN FROM VCC 2D 13-SW-138 SERVICE WATER RETURN FROM VCC 2A 13-SW-141 LARGE PIPEISOhETRIC SERVICE WATER RETURN 2 - 13 Resision 0
~ -.
. - - ~.
ANO Unit 13 Interval Inservice Inspection Plan TABLE 2.3 PIPING ISOMETRIC DRAWINGS (con't)
L 1
l DRAWING TITLE NUMBER i
13-SW-142 LARGE PIPE ISOMETRIC SERVICE WATER SUPPLY ESSENTIAL 13-SW-143.
LARGE PIPEISOMETRIC (Sheets 1 and 2)
SERVICE WATER RETURN FROM E20B1 AND E20B2 FOR l
K4B l
13-SW-149 LARGE PIPEISOMETRIC CONTAINMENT COOLING COIL VCC 2D SUPPLY AND RETURN PIPING l
13-SW-150 LARGE PIPE ISOMETRIC CONTAINMENT COOLING COIL VCC 2B SUPPLY AND j
RETURN PIPING 13-SW-151 SERVICE WATER CONNECTIONS FOR VCC 2C l
I 13-SW-152 LARGE PIPEISOMETRIC l
SERVICE WATER SUPPLY AND RETURN FOR REACTOR
)
BUILDING COOLING COIL VCC 2A 13-SW-154 LARGE PIPE ISOMETRIC SERVICE WATER RETURN l
13-SW-156 LARGE PIPEISOMETRIC i
SERVICE WATER SUPPLY j
l 13-SW-162 LARGE PIPEISOMETRIC I
SERVICE WATER SUPPLY ESSENTIAL I
16-RC-4 LARGE PIPEISOMETRIC L
PRESSURIZER RELIEF PIPING FROM PSV-1001 TO QUENCH TANK T-42 16-RC-6 LARGE PIPEISOMETRIC PRESSURIZER RELIEF DOWNSTREAM OF RELIEF VALVE PSV-1000 16-RC-8 LARGE PIPE ISOMETRIC PRESSURIZER RELIEF PIPING FROM PSV-1002 TO QUENCH TANK T-42 16-RC-9 PRESSURIZER MAIN SPRAY LIhT CCA-4 17-MU-1 LARGE PIPE ISOMETRIC l
SYSTEM #17 MAKE UP & PURIFICATION 17-MU-2 LARGE PIPE ISOMETRIC (Sheet 1)
MAKE UP & PURIFICATION j
17-MU-2 LARGE PIPEISOMETRIC
{
l (Sheet 2)
MAKE UP & PURIFICATION FROM LETDOWN COOLERS TO DECAY TANK l
l
.2 - 14 Revision 0
o d
ANO Unit 13 Interval Inservice Inspection Plan TABLE 2.3 PIPING ISOMETRIC DRAWINGS (con't)
DRAWING TITLE NUMBER 17-MU-17 LARGE PIPE ISOhETRIC MAKE-UP PUMP SUCTION 17-MU-l8 LARGE PIPE ISOhETRIC MAKE-UP PUMP SUCTION 17-M~U-19 LARGE PIPE ISOMETRIC MAKE-UP PUMP SUCTION 17-MU-20 LARGE PIPE ISOhETRIC MAKE-UP PUMP DISCHARGE 17-MU-21 LARGE PIPE ISOMETRIC SEAL FLOW TO REACTOR COOLANT PUMPS l
17-MU-22 LARGE PIPEISOhETRIC i
MAKE UP TO REACTOR COOLANT SYSTEM 17-MU-23 LARGE PIPEISOMETRIC RCP P-32D HP INJECTION AND CROSS CONNECTION 17-MU-24 LARGE PIPE ISOMETRIC HP INJECTION TO RCS 17-MU-25 LARGE PIPE ISOMETRIC HIGH PRESSURE INJECTION TO REACTOR COOLANT SYSTEM 17-MU-26 LARGE PIPE ISOhETRIC HP INJECTION TO REACTOR COOLANT PUMP P-32A 17-MU-27 LARGE PIPE ISOhETRIC HP INJECTION TO REACTOR COOLANT PUMP P-32B 17-MU-28 LARGE PIPEISOhETRIC HIGH PRESSURE INJECTION TO REACTOR COOLANT SYSTEM 17-MU-29 LARGE PIPE ISOhETRIC HIGH PRESSURE INJECTION TO REACTOR COOLANT PUMP P-32C (LOOP C) 17-MU-30 LARGE PIPEISOhETRIC P-32C HP INJECTION 17-MU-31 LARGE PIPE ISOhETRIC j
HIGH PRESSURE INJECTION TO REACTOR COOLANT PUMP P-32D 1
17-MU-37 LARGE PIPE ISOhETRIC REDUNDANT HPI INJECTION TO REACTOR COOLANT SYSTEM OUTSIDE CONTAINhENT : LOOPS "A" & "B" 2 - 15 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 2.3 PIPING ISOMETRIC DRAWINGS (con't)
DRAWING TITLE NUMBER i
y,,.
j l 17 MU-38 LARGE PIPEISOMETRIC l
REDUNDANT HPI INJECTION TO REACTOR COOLANT j
l i
SYSTEM OUTSIDE CONTAINMENT : LOOPS "C" & "D" I
l LWA-200 SMALL PIPEISOMETRIC REACTOR COOLANT PUMP P-32A & B DRAINS TO l
REACTOR BUILDING DRAIN HEADER LWA-201 SMALL PIPEISOMETRIC REACTOR COOLANT SYSTEM VENTS, DRAINS AND MISCELLANEOUS PIPING MS-210 SMALL PIPEISOMETRIC STEAM TRAP 5 PIPING MU-200 SMALL PIPEISOMETRIC i
MAKE-UP PUMP DISCHA'lGE 2P-36A, B & C DISCHARGE t
TO 2E-26A & B MU-201 SMALL PIPEISOMETRIC PRIMARY MAKE-UP PUMP P-36A, B & C DISCHARGE TO SEAL RETURN COOLERS E-26A & B i
MU-204 SMALL PIPEISOMETRIC j
SEAL FLOW TO REACTOR COOLANT PUMPS MU-206 SMALL PIPEISOMETRIC P-32D CONTROLLED BLEED OFF J
MU-210 SMALL PIPEISOMETRIC P-32D SEALINJECTION MU-219 SMALL PIPEISOMETRIC REACTOR COOLANT PUMP, P-32A CONTROLLED BLEED OFF MU-220 SMALL PIPE ISOMETRIC REACTOR COOLANT PUMP, P-32C SEAL INJECTION '
i MU-221 SMALL PIPEISOMETRIC P-32A SEALINJECTION MU-223 SMALL PIPEISOMETRIC REACTOR COOLANT PUMP, P-32B SEAL INJECTION MU-224 SMALL PIPE ISOMETRIC REACTOR COOL ANT PUMP P-32B CONTROLLED BLEED OFF PIPING
[-
MU-225 SMALL PIPEISOMETRIC REACTOR COOLANT PUMP P-32C CONTROLLEO BLEED OFF PIPING f-RC-203 PRESSURIZER AUX. SPRAY LINE CCA-9 & CCB-9 j
l i
i l
2 - 16 Revision 0 i
L l
1 ANO Unit 13"' Interval 4
InserviceInspection Plan I
i SECTION 3.0 l
INSERVICE INSPECTION PIPING LINE LIST l
i l
The Inservice Inspection Piping Line List is a tabulation of the ASME Code Class 1, 2 and 3 lines j
at ANO-1. ' Also included are those lines that are " treated as ISI Class 2 (T2)" and " treated as ISI i
Class 3 (T3)". [Certain sections of piping designated as design Class 3 or non-classed have been l
i upgraded to Class T2, while other sections of non-classed piping were upgraded to Class T3 for i
inspection and testing purposes. This was done to provide consistency between the ANO-1 and Arkansas Nuclear One, Unit Two (ANO-2), ISI Plans.] The table includes pertinent information
- on the piping lines within the inservice inspection boundaries.
r Under the heading of" Safety Function," the following safety function abbreviations have been assigned to Class 2,3, T2 and T3 lines. If a particular line serves more than one safety function, t
each one will be listed.
i "R" - Reactor Residual Heat Removal (RHR) f "E" - Emergency Core Cooling (ECC)
'.'C" - Containment Heat Removal (CHR) i-
"A" - Atmosphere Cleanup
' i l.
The following assumptions were used as the basis for the line list:
i i
j
- 1) All vent and drain line are not assigned a safety function.
i j
- 2) Lines to safety valves which are passive in design basis accidents and only provide for i
system overpressure protection are not assigned a safety function.
- 3) Sodium hydroxide tank outlets are assigned an "A" safety function.
j
- 4) Service Water lines are assigned the same function as the component (s) they serve.
- 5) Reactor Building sump recirculation lines are not assigned an "R" safety' function.
l They are listed as an "E" since they serve an ECC function.
- 6). Class 1,2, and 3 tubing is typically not assigned a specific line number.
- 7) The Emergency Feedwater (EFW) pump recirculation lines are included since they are not isolated on EFW actuation.
- 8) Lo'w Pressure Injection recirculation lines are included since they are unisolable, f
- 9) High Pressure Injection pump recirculation lines beyond the applicable isolation valves are excluded since they are isolated on ECC actuation.
- 10) Test loops and system interconnections that are provided for operational convenience are not assigned a safety function.
a 4
4 1
i ~
3-1 Revision 0 4
(
v
ANO Unit 13"' Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION CCA-01 28 M-230-1 RCS 1
CCA-01 36 M-230-1 RCS 1
CCA-01 1
M-230-1 RCS 1
IWB-1220(bXI) -
CCA-02 10 M-230-1 RCS 1
CCA-03 0.5 M-231-2 RCS 1
IWB-1220(bXI)
CCA-03 1
M-230-1 RCS 1
IWB-1220(bXI)
CCA-03 2.5 M-230-1 RCS 1
CCA-04 0.5 M-230-1 RCS 1
IWB-1220(bXI)
CCA-04 2.5 M-230-1 RCS 1
CCA-04 4
M-230-1 RCS 1
CCA-05 2.5 M-230-1 RCS 1
CCA-05 3
M-230-1 RCS 1
CCA-05 4
M-230-1 RCS I
CCA-06 8
M-230-1 RCS I
CCA-06 12 M-230-1 RCS I
CCA-06 1
M-230-1 RCS 1
nWB-1220(bXI)
CCA-06 14 M-230-1 RCS 1
CCA-07 3
M-230-1 RCS 1
CCA-08 l 12 M-220-1 RCS 1
3-2 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan e
TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (com't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMFI1ON BAS 6S NO.
(IN)
CLASS FUNCTION CCA-09 1.5 M-230-1 RCS~
l
[
CCA-13 0.75 M-230-1 RCS 1
IWB-1220(bXI)
CCA-13 1
M-230-1
' RCS 1
IWB-1220(bXI)
CCA-13 1.5 M-230-1 RCS 1
CCA-14 0.5 M-235-1 RCS 1
IWB-1220(bXI)
CCA-15 1
M-230-2 RCS 1
IWB-1220(bXI)
CCB-01 1.5 M-232-1 DHR 2
R IWC-1221(aXI)
CCB-01.
2 M-232-1 DHR 2
R IWC-1221(aXI)
CCB-01 8
M-230-1 DHR 2
E,R CCB-01 12 M-230-1 DHR.
2 E,R CCB-02 0.75 M-231-2 MU 2
IWC-1222(a)
CCB-02 2.5 M-231-2 MU 2
IWC-1222(a) l CCB-03 0.5 M-231-2 MU 2
IWC-1222(a) f CCB-03 1.5 M-231-2 MU 2
IWC-1222(a)
CCB-03 2.5 M-231-2 MU 2
IWC-1222(a)
CCB-04 0.75 M-231-1 MU 2
IWC-1222(a) r CCB-04 1.5 M-231-1 MU 2
IWC-1222(a)
CCB-04 2
M-231-1 MU 2
IWC-1222(a)
CCB-04 4
M-231-1 MU 2
E
~
3-3 Revision 0 l
ANO Unit 13 Interval Inservice Inspection Plan P
TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&lD SYS.
ISI SAFETY EXEMITION BASIS NO.
(IN)
CLASS FUNCTION CCB-05 2.5 M-231-3 MU 2
E CCB-05 3
M-231-3 MU 2
E CCB-05 4
M-231-1 MU 2
E CCB4)6 14 M-236-1 CF 2
E IWC-1221(c)
CCB-07 3
M-231-1 MU 2
E CCB-07 4
M-231-1 MU 2
E CCB-07 1
M-231-1 MU 2
E IWC-1221(b)(1)
CCB-07 2
M-231-1 MU 2
IWC-1222(a)
[
CCB-08 1
M-231-1 MU 2
E IWC-1221(b)(1)
CCB-08 2.5 M-231-1 MU 2
IWC-1222(a)
CCB-09 0.5 M-232-1 DH 2
IWC-1222(a)
CCB-09 1.5 M-232-1 DH 2
IWC-1222(a)
CCB-09 2.5 M-231-1 MU 2
E IWC-1221(a)(1) t CCB-10 1
M-231-1 MU 2
IWC-1222(a) f CCB-10 2.5 M-231-1 MU 2
IWC-1222(a) l CCB-11 0.75 M-237-1 SMP 2
IWC-1222(a)
CCB-11 0.5 M-237-1 SMP 2
IWC-1222(a)
CCB-12 0.5 M-237-1 SMP 2
IWC-1222(a)
CCB-12 0.75-M-237-1 SMP 2
IWC-1222(a) 3-4 l
Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION i
CCB-12 1
M-237-1 SMP 2
IWC-1222(a)
CCB-12 1.5 M-237-1 SMP 2
IWC-1222(a)
CCB-13 1
M-230-2 RCS 2
IWC-1222(a)
CCB-15 0.75 M-238 RCP 2
IWC-1222(a)
CCB-16 1
M-231-2 MU 2
IWC-1222(a)
CCB-17 1
M-230-2 RCS 2
IWC-1222(a)
CCB-18 1
M-230-2 RCS 2
IWC-1222(a)
CCB-19 1
M-230-2 RCS 2
IWC-1222(a)
CCB-20 1
M-230-1 RCS 2
IWC-1220(a)
CCB-21 1.25 M-231-1 MU 2
IWC-1222(a)
CCC-01 1.5 M-238 RCP 3
IWD-1220(aXI)
CCC-02 0.75 M-238 RCP 3
IWD-1220(aXI)
CCC-03 0.75 M-238 RCP 3
IWD-1220(aXI) l CCC-04 1.5 M-238 RCP 3
IWD-1220(aXI)
CCC-05 0.75 M-231-2 MU 3
IWD-1220(aXI)
CCC-05 1
M-231-2 MU 3
IWD-1220(aXI)
CCC-06 I
M-230-1 RBS 3
IWD-1220(aXI)
DBD-01 0.75 M-204-3 EFW T3 IWD-1220(bXI)
DBD-01 6
M-204-3 EFW T3 R
[
3-5 Revision 0
ANO Unit 13'd Interval Inservice Inspection Plan -
TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION DBD-01 1
M-204-3 EFW
'I3 IWD-1220(bXI)
DBD-01 4
M-204-3 EFW T3 R
DBD-02 0.75 M-204-3 EFW T3 IWD-1220(bXI)
DBD-02 1
M-204-3 EFW T3 IWD-1220(bXI)
DBD-02 4
M-204-3 EFW T3 R
DBD-02 6
M-204-3 EFW T3 R
DBD-03 0.75 M-204-3 EFW T3 IWD-1220(bXI)
DBD-03 1
M-204-3 EFW T3 IWD-1220(bXI)
DBD-03 4
M-204-3 EFW T3 R
DBD-03 6
M-204-3 EFW T3 R
DBD-04 0.75 M-204-3 EFW T3 IWD-1220(bXI)
DBD-04 4
M-204-3 EFW T3 R
DBD-05 4
M-204-3 EFW
'13 R
DP')-05 0.75 M-204-3 EFW T3 IWD-1220(bXI)
EBB-01 18 M-206-1 FW 2
EBB-01 14 M-206-1 FW 2
EBB-02 1
M-204-3 EFW 2
IWC-1221(aXI)
EBB-02 4
M-204-3 EFW 2
R IWC-1221(aXI) s EBB-02 6
M-206-1 EFW 2
R 3-6 Revision 0 l
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&lD SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION EBB-03 0.75 M-206-1 MS 2
IWC-1222(a)
EBB-03 4
M-204-6 MS 2
R IWC-1222(a)
EBB-03 8
M-206-1 MS 2
R EBB-03 10 M-206-1 MS 2
R EBB-03 24 M-206-1 MS 2
R EBB-03 26 M-206-1 MS 2
R EBB-03 36 M-206-1 MS 2
R EBB-03 36 M-206-1 MS 2
R EBB-04 4
M-206-1 MS 2
IWC-1222(a)
EBB-05 0.75 M-206-1 MS 2
IWC-1222(a)
EBB-05 1.5 M-206-1 MS 2
IWC-1222(a)
EBB-06 0.75 M-206-1 MS 2
IWC-1222(a)
EBB-06 1.5 M-206-1 MS 2
IWC-1222(a)
EBD-01 36 M-206-2 MS None EBD-03 8
M-206-1 MS T2 R
EBD-03 10 M-206-1 MS T2 R
EBD-06 3
M-204-6 MS T3 R
IWD-1220(a)(1)
EBD-06 4
M-204-6 MS T3 R
IWD-1220(a)(1) l EBD-06 0.75 M-204-6 MS T3 R
IWD-1220(a)(1) i 3-7 Revision 0 m
...m.
.2.
m.
- m.. -...
.m..-
m-m-m
.m m
2
-r
-a mu--+
+e*
---e w
a m
.a a
m m m
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.I INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE PalD SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION EBD-06 6
M-204-6 MS T3 R
EBD-10 18 M-206-1 FW None EBD-Il 0.75 M-204-3 EFW T3 IWD-1220(bXI)
EBD-Il 1
M-204-3 EFW T3 IWD-1220(bXI)
EBD-11 2
M-204-3 EFW T3 R
EBD-Il 4
M-204-3 EFW T3 R
EBD-18 0.75 M-204-6 MS T3 R
IWD-1220(aXI)
EBD-27 4
M-204-6 MS T3 R
IWD-1220(aXI) i EBD-28 0.75 M-204-6 MS T3 R
IWD-1220(aXI)
ECB-01 0.75 M-206-1 MS 2
IWC-1222(a)
ECB-02 0.75 M-206-1 MS 2
IWC-1222(a)
FCB-01 1
M-236-1 CF 2
E IWC-1221(aXI)
FCB-02 0.5 M-230-1 CZ None R.G.1.26 FCB-02 0.75 M-230-1 CZ None R.G.1.26 i
FCB-02 1
M-230-1 CZ None R.G.1.26 FCB-02 3
M-230-1 CZ None R.G.1.26 FCB-02 6
M-230-1 CZ None R.G.1.26 FCB-02 10 M-230-2 CZ None R.G.1.26 FCB-03 1
M-236-1 CF 2
E IWC-1221(aXI) 3-8 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan -
TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION FCB-03 14 M-236-1 CF 2
E IWC-1221(c)
GCB-01 1.5 M-232-1 DHR 2
IWC-1222(a)
GCB-01 10 M-232-1 DHR 2
E,R j
GCB-01 8
M-232-1 DHR 2
GCB-01 6
M-232-1 DHR 2
E,R GCB-01 2
M-232-1 DHR 2
E,R IWC-1221(aXI)
GCB-01 1
M-232-1 DHR 2
IWC-1222(a) i i
GCB-01 0.75 M-232-1 DHR 2
IWC-1222(a)
GCB-01 2.5 M-232-1 DHR 2
E,R IWC-1221(aXI)
GCB-02 6
M-231-1 MU 2
E GCB-02 4
M-231-1 MU 2
E IWC-1221(aXI)
GCB-02 0.75 M-231-1 MU 2
E IWC-1221(aXI)
GCB-02 2
M-231-1 MU 2
E IWC-1221(aXI)
GCB-03 3
M-232-1 DHR 2
R,E IWC-1221(aXI) i GCB-03 4
M-231-1 MU 2
R,E IWC-1221(aXI)
GCB-04 0.75 M-232-1 DHR 2
IWC-1222(a)
GCB-04 2
M-232-1 DHR 2
E,R IWC-12.22(a)
GCB-04 2.5 M-232-1 DHR 2
IWC-1222(a) y-GCB-04 3
M-232-1 DHR 2
l IWC-1222(a) 3-9 Revision 0 l
2
ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 l
INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE PalD SYS.
ISI SAFETY EXEMFilON BASIS NO.
(IN)
CLASS FUNCTION GCB-04 12 M-232-1 DHR 2
E,R GCB-04 14 M-232-1 DHR 2
E,R GCB-06 1
M-231-1 MU 2
E IWC-1221(a)(1)
GCB-06 6
M-231-1 MU 2
E GCB-10 8
M-232-1 DHR 2
GCB-12 8
M-236 BS 2
C GCB-12 2
M-236 BS 2
IWC-1222(a)
GCB-12 6
M-236 BS 2
GCB-15 0.75 M-232-1 DHR 2
IWC-1222(a)
GCB-15 2
M-231-1 GRW 2
IWC-1222(a)
GCB-16 1
M-232-1 DHR 2
IWC-1222(a)
GCC-01 0.75 M-232 DHR 3
IWD-1220(a)(1)
GCC-01 2.5 M-232-1 DHR 3
IWD-1220(a)(1)
HBB-01 1
M-218 SA 2
IWC-1222(a)
HBB-02 8
M-234-1 ICW 2
IWC-1222(d)
HBB-03 0.75 M-210 SW 2
IWC-1222(a)
HBB-03 10 M-210 SW 2
C HBB-04 2
M-215 GRW 2
IWC-1220(a)
HBB-05 6
M-222 AC 2
IWC-1222(c) 3-10 Kevision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HBB-07 3
M-220 AC 2
IWC-1222(a)
HBB-08 1
M-233 N2 2
R.G.1.26 i
HBB-08 10 M-233 N2 2
R.G.1.26 I
HBB-09 3
M-219-1 FP 2
IWC-1222(a)
HBB-10 3
M-236 ILRT 2
IWC-1220(a) 4 HBB-13 2
M-261-3 CAF 2.
IWC-1220(a) l HBB-14 0.5 M-261-3 CAF 2
IWC-1220(a)
HBB-14 0.75 M-261-3 CAF 2
IWC-1220(a)
HBB-14 2
M-261-3 CAF 2
IWC-1220(a)
HBB-15 0.75 M-261-3 CAF 2
IWC-1220(a)
HBB-15 1
M-261-3 CAF 2
IWC-1220(a)
HBB-15 2
M-261-3 CAF 2
IWC-1220(a)
HBB-16 0.75 M-261-1 RBHV 2
IWC-1220(a)
HBB-16 54 M-161-1 RBHV 2
IWC-1220(c)
HBB-17 0.75 M-261-1 RBHV 2
IWC-1220(a)
HBB-17 54 M-261-1 RBHV 2
IWC-1220(c) f HBC-01 0.75 M-237-4 SMP 3
IWD-1220(a)(1)
HBC-01 1
M-261-3 CAF 3
IWD-1220(a)(1)
HBC-01 2
M-261-3 CAF 3
A IWD-1220(a)(1) i 3-11 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HBC-01 0.25 M-261-3 CAF 3
IWD-1220(aXI)
HBC-02 1.25 M-261-3 CAF 3
A IWD-1220(aXI)
HBC-02 2
M-261-3 CAF 3
A IWD-1220(aXI)
HBC-02 1
M-261-3 CAF 3
IWD-1220(aXI)
?
HBC-02 0.75 M-237-4 SMP 3
IWD-1220(aXI)
HBC-02 0.25 M-261-3 CAF 3
A IWD-1220(aXI)
HBC-02 3
M-261-3 CAF 3
A IWD-1220(aXI)
HBD-02 0.75 M-209-1 SW T3 C,R,E IWD-1220(aXI)
HBD-02 18 M-209-1 SW T3 C,R,E HBD-04 1
M-204-3 EFW T3 IWD-1220(bXI)
HBD-04 6
M-204-3 SW T3 R
HBD-04 4
M-204-3 SW T3 C,R,E IWD-1220(aXI)
HBD-04 8
M-204-3 EFW T3 R
HBD-04 0.75 M-204-3 SW T3 IWD-1220(aXI)
HBD-13 3
M-210 SW T3 C,R,E IWD-1220(aXI)
HBD-13 18 M-210 SW T3 C,R,E HBD-14 14 M-210 SW T3 C,R,E HBD-14 18 M-2t Al SW T3 C,R.E HBD-14 12 M-210 SW T3 C,R,E 3-12 Revision 0
~
ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't) t LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HBD-14 10 M-210 SW T3 C,R,E HBD-14 8
M-210 SW T3 C
HBD-14 4
M-210 SW T3 C,R,E IWD-1220(aXI)
HBD-14 1.5 M-210 SW T3 C,R,E IWD-1220(aXI)
HBD-14 1
M-209-1 SW T3 C,R,E IWD-1220(aXI) j HBD-14 0.75 M-209-1 SW T3 C,R,E IWD-1220(aXI)
HBD-14 0.5 M-210 SW T3 C,R,E IWD-1220(aXI) t HBD-14 2
M-209-1 SW T3 C,R,E IWD-1220(aXI)
HBD-19 0.75 M-204-3 EFW T3 IWD-1220(bXI) j HBD-19 4
M-204-3 EFW T3 R
HBD-20 12 M-210 SW T3 C,R,E
[
HBD-20 14 M-210 SW T3 C,R,E HBD-20 2
M-209-1 SW T3 C,R,E IWD-1220(aXI)
HBD 18 M-209-1 SW T3 C,R,E HBD-21 0.75 M-210 SW T3 C,R,E IWD-1220(aXI)
HBD-21 1
M-210 SW T3 C,R,E IWD-1220(aXI) i HBD-21 2
M-210 SW T3 E
IWD-1220(aXI)
HBD-21 3
M-210 SW T3 C,R.E IWD-1220(aXI)
HBD-21 4
M-210 SW T3 C,R,E IWD-1220(a)(1) 3-13 Revision 0 i
ANO Unit 13"' Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HBD-21 8
M-210 SW T3 C
HBD-21 10 M-210 SW T3 C
HBD-21 12 M-210 SW T3 C,R,E HBD-21 18 M-210 SW T3 C,R,E HBD-24 8
M-204-3 EFW T3 R
HBD-24 0.75 M-204-3 EFW T3 IWD-1220(bXI)
HBD-42 0.75 M-210 SW E
IWD-1220(aXI)
HBD-43 0.75 M-204-6 MS T3 R
IWD-1220(bXI)
[
HBD-43 1
M-204-6 MS T3 R
IWD-1220(bXI)
HBD-45 10 M-210 SW T3 C
HBD-45 0.75 M-210 SW T3 C,R,E IWD-1220(aXI)
[
HBD-45 1
M-210 SW T3 C
IWD-1220(aXI)
HBD-46 1.5 M-210 SW T3 C,R,E IWD-1220(aXI)
HBD-46 10 M-210 SW T3 C
HBD-46 0.75 M-210 SW T3 IWD-1220(aXI)
HBD-56 0.5 M-210 SW T3 0-1220(aXI)
HCB-01 1.5 M-236 BS 2
IWC-1222(a)
I IICB-01 8
M-236 BS 2
C HCB-02 1
M-232-1 DHR 2
IWC-1222(a) 3-14 i
Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1
[
INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HCB-02 20 M-232-1 BWST 2
'C,R,E f
HCB-02 14 M-232-1 BWST 2
C,R,E
[
HCB-02 6
M-232-1 BWST 2
E HCB-02 1.5 M-232-1 DHR 2
C,R,E IWC-1221(a)(1)
HCB-02 0.75 M-232-1 DHR 2
IWC-1222(a)
HCB-02 4
M-232-1 BWST 2
C,R,E IWC-1221(a)(1)
HCB-03 10 M-235-1 SF 2
IWC-1222(c)
HCB-03 3
M-235-1 SF 2
IWC-1222(a)
HCB-03 8
M-235-1 SF 2
IWC-1222(c)
HCB-05 3
M-230-2 CZ 2
IWC-1222(a)
HCB-05 4
M-213-2 RW 2
IWC-1222(a)
HCB-06 0.75 M-236 BS 2
C IWC-1221(a)(1) i HCB-06 1
M-236 BWST 2
IWC-1222(a) l HCB-06 4-M-236 BWST 2
C IWC-1221(a)(1)
HCB-06 8
M-236 BWST 2
C 1
HCB-06 10 M-232-1 BWST 2
C f
HCB 3 M-234-1 CRD 2
IWC-1222(a) l HCB-09 1
M-237-1 SMP 2
IWC-1220(a)
HCB-09 0.75 M-237-1 SMP 2
IWC-1220(a) 3-15 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HCB-11 0.5 M-235-1 SF 2
IWC-1222(a)
HCB-11 2
M-235-1 SF 2
IWC-1222(a)
HCC-01 3
'M-231-2 MU 3
IWD-1220(aXI)
HCC-01 4
M-232 MU 3
IWD-1220(aXI)
HCC-01 1
M-231-1 MU 3
IWD 1220(aXI)
HCC-01 2
M-231 MU 3
IWD-1220(aXI)
HCC-01 2.5 M-231-1 MU 3
IWD-1220(aXI)
HCC-02 0.5 M-230 MU 3
IWD-1220(aXI)
HCC-03 0.5 M-230 MU 3
IWD-1220(aXI)
HCC-04 1.5 M-231-2 MU 3
IWD-1220(aXI)
HCC-04 2.5 M-231-2 MU 3
IWD-1220(aXI)
HCC-05 1
M-231-2 MU 3
IWD-1220(aXI)
HCC-05 2
M-231-2 MU 3
IWD-1220(aXI)
HCC-05 3
M-231-1 MU 3
IWD-1220(aXI)
HCC-08 2.5 M-231-1 MU 3
IWD-1220(aXI)
HCC-08 4
M-231 MU 3
IWD-1220(aXI)
HCC-09 6
M-235-1 SF 3
IWD-1220(c)
HCC-09 10 M-235-1 SF 3
IWD-1220(c)
HCC-09 1
M-235-1 SF 3
IWD-1220(aXI) 3-16 Revision 0
ANO Unit 13"' Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HCC-10 1
M-235-1 SF 3
IWD-1220(aXI)
HCC-10 3
M-235-1 SF 3
IWD-1220(aXI)
HCC-10 8
M-235-1 SF 3
IWD-1220(c)
HCC-Il 3
M-235-1 SF 3
IWD-1220(aXI)
HCC-12 3
M-235-1 SF 3
IWD-1220(aXI)
HCC-12 4
M-235-1 SF 3
IWD-1220(aXI)
HCC-12 0.5 M-214-1 LRW 3
IWD-1220(aXI) l HCC-12 6
M-235-1 SF 3
IWD-1220(c)
HCC-13 3
M-235-1 SF 3
IWD-1220(aXI)
HCC-14 2
M-235-1 SF 3
IWD-1220(aXI)
HCC-14 4
M-235-1 SF 3
IWD-1220(aXI) i HCC-14 10 M-235-1 SF 3
IWD-1220(c) i HCC-15 3
M-235-1 SF 3
IWD-1220(aXI)
HCC-15 0.75 M-235-1 SF 3
IWD-1220(aXI)
HCC-15 6
M-235-1 SF 3
IWD-1220(c)
HCC-15 1
M-235-1 SF 3
IWD-1220(aXI)
HCC-15 2
M-235-1 SF 3
IWD-1220(aXI)
HCC-16 4
M-235-1 SF 3
IWD-1220(aXI)
HCC-17 0.25 M-231-1 MU 3
IWD-1220(aXI) 3-17 Revision 0 l
- - = -
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d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (com't)
[
LINE SIZE PalD SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION j
HCC-29 4
M-204-5 CST 3
IWD-1220(aXI)
I HCC-30 6
M-204-5 CST 3
R HCC-31 3
!M-232-1 BW T2 IWC-1222(a)
HCC-32 3
M-232-1 BW T2 IWC-1222(a)
{
HCD-03 8
M-232-1 BW T2 C,R,E HCD-03 4
M-232-1 BW T2 C,R,E IWC-1221(aXI)
HCD-03 3
M-232-l '
BW T2 C,R,E IWC-1221(aXI)
HCD-03 1
M-232-1 BW T2 IWC-1221(aXI)
HCD-06 1
M-233 BS T3 A
IWD-1220(aXI) l i
t HCD-06 2
M-233 BS T3 A
IWD-1220(aXI) '
f HCD-06 3
M-233 BS T3 A
IWD-1220(aXI)
HCD-06 4
M-233 -
BS T3 A
IWD-1220(aXI) l HCD-06 6
M-233 BS T3 A
IWD-1220(c)
HCD-08 8
M-236 BS T2 C
IWC-1222(d) i HCD-Ill 6
M-210 SW T3 C,R,E HCD-Ill 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-111 2
M-210 SW T3 C,R,E
. IWD-1220(aXI)
HCD-111 4
M-210 -
SW T3 C,R,E IWD-1220(aXI)
HCD-Il2 6
M-210 SW.
T3 C,R,E l
3-19 Revision 0 l
i
. m
. m m.
.. m.
m w-m
=r
-- --.w-.-
-m-
l d
ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION 1
HCD-Il2 4
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-Il2 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-Il2 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-113 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-Il3 1.5 M-210 SW T3 IWD-1220(aXI)
HCD-Il3 3
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-113 4
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-Il3 6
M-210 SW T3 C,R,E HCD-Il3 8
M-210 SW T3 C,R,E HCD-Il4 0.75 M-210 SW T3 IWD-1220(aXI) l HCD-Il4 3
M-210 SW T3 E
IWD-1220(aXI)
HCD-Il4 4
M-210 SW T3 C,R,E IWD-1220(aXI)
I HCD-115 4
M-210 SW T3 C,R,E IWD-1220(aXI) i HCD-IIS 3
M-210 SW T3 C,R,E IWD-1220(aXI) i l
HCD-Il5 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-Il6 4
M-210 SW T3 R,E IWD-1220(aXI)
HCD-Il6 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-Il6 3
M-210 SW T3 R,E IWD-1220(aXI)
HCD-117 0.75 M-210 SW T3 IWD-1220(aX1) 3-20 Revision 0
l d
ANO Unit 13 Interval Inservice Inspection Plan TADLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI-SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HCD-Il7 3
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-Il8 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-118 3
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-Il8 6
M-210 SW T3 C,R,E HCD-123 1
M-209-1 SW T3 IWD-1220(aXI)
HCD-123 2
M-209-1 SW T3 R
IWD-1220(aXI)
HCD-124 8
M-210 SW T3 C
HCD-125 8
M-210 SW T3 C
HCD-15 4
M-232-1 BW T2 C,R,E HCD-15 20 M-232-1 BW T2 C,R,E HCD-24 2
M-235 SF T3 IWD-1220(aXI)
HCD-28 0.5 M-210 SW T3 IWD-1220(aXI)
HCD-29 0.5 M-210 SW T3 IWD-1220(aKI)
~
HCD-34 1.5 M-210 SW T3 IWD-1220(aXI)
HCD-34 0.75 M-210 SW 3
C,R,E IWD-1220(aXI)
HCD-34 1.25 M-210 SW 3
IWD-1220(aXI) s HCD-34 1.5 M-210 SW 3
IWD-1220(aXI)
HCD-36 2
M-210 SW T3 R,E IWD-1220(aXI)
HCD-37 1.5 M-210 SW T3 C,R,E IWD-1220(aXI) 3-21 Revision 0
~
.-...=
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (com't) -
LINE SIZE P&ID SYS.
ISI SAFETY EXE=MPTION BASIS NO.
(IN)
CLASS FUNCTION l
HCD-37 2
M-210 SW T3 R,E IWD-1220(aXI)
HCD-37 0.75 M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-38 2
M-210 SW T3 R,E IWD-1220(aXI)
HCD-39 1
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-39 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-40 1
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-40 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD41 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-42 1
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-42 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-43 1-M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-44 1
M-210 SW T3 E
IWD-1220(aXI)
[
HCD45 1
M-210 SW T3 E
IWD-1220(aXI) l HCD-46 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-46 1
M-210 SW T3 E
IWD-1220(aXI)
HCD-47 1.5 M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-48 0.75 M-210 SW T3 IWD-1220(aXI) j HCD-48 1.5 M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-49 1.5 M-210 SW T3 C,R,E IWD-1220(aXI) 3-22 Revision 0
n d
ANO Unit 13 Interval-Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HCD-49 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-50 0.75 M-210 SW T3 IWD-1220(aXI)
HCD-50 1.5 M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-54 1.25 M-210 SW T3 IWD-1220(aXI)
, MCD-54 1.5 M-210 SW T3 IWD-1220(aXI)
' HCD-55 1
M-210 SW
~D IWD-1220(aXI)
HCD-56 2
M-210 SW T2 C,R,E IWD-1220(a)(1)
HCD-56 1.5 M-210 SW T3 IWD-1220(aXI)
HCD-56 1.25 M-210 SW T3 IWD-1220(aXI)
HCD-57 1
M-210 SW T3 IWD-1220(aXI)
HCD-58 2
M-210 SW T3 IWD-1220(aXI)
HCD-59 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD40 2
M-210 SW T3 E
IWD-1220(aXI)
HCD-61 1
M-210 SW T3 IWD-1220(aXI)
HCD41 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD42 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD42 1
M-210 SW T3 PND-1220(aXI)
HCD43 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD44 1
M-210 SW T3 IWD-1220(aXI) 3-23 Revision 0
ANO Unit 13'd Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID
- SYS, ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HCD-64 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-65 2
M-210 SW T3 C,R,E IWD-1220(aXI) -
HCD-65 0.75 M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-66 0.75 M-210 SW T3 C,R,E g IWD-1220(aXI)
HCD-66 2
M-210 SW T3 C,R,E IWD-1220(aXI)
HCD-97 6
M-204-5 CST T3 R
HDB-08 3
M-230 CS 2
IWC-1222(a)
HRC-01 2
M-214-1 LRW 3
IWD-1220(aXI)
HRC-02 1
M-215-1 GRW 3
IWD-1220(aXI)
[
HRC-02 2
M-215-1 GRW 3
IWD-1220(aXI)
HRC-03 0.75 M-215-1 GRW 3-IWD-1220(aX1)
HRC-03 3
M-215-1 GRW 3
IWD-1220(aXI) h'RC-03 2.5 M-215-1 GRW 3
IWD-1220(aXI)
HRC-03 1
M-215-1 GRW 3
IWD-1220(aXI)
HRC-03 0.5 M-215-1 GRW 3
IWD-1220(aXI)
HRC-03 2
M-215-1 GRW 3
IWD-1220(aXI)
HRC-04 0.5 M-215-1 GRW 3
IWD-1220(aXI)
HSC-01 3
M-214-1 LRW 3
IWD-1220(aXI)
HSC-01 1.5 M-214-1 LRW 3
IWD-1220(aXI) t 3-24 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HSC-01 4
M-214-1 LRW 3
IWD-1220(a)(1)
HSC-01 2
M-214-3 LRW 3
IWD-1220(aXI)
HSC-01 0.75 M-213-1 RW 3
IWD-1220(aXI) i HSC-01 2.5 M-214-2 LRW 3
IWD-1220(aXI)
HSC-02 1
M-214-3 LRW 3
IWD-1220(a)(1)
HSC-02 1.5 M-214-3 LRW 3
IWD-1220(aXI)
L HSC-02 2
M-231-2 MU 3
IWD-1220(aXI) t HSC-02 2.5 M-231-2 MU 3
IWD-1220(a)(1)
HSC-02 3
M-231-2 MU 3
IWD-1220(aXI)
HSC-03 3
M-230-2 CZ 3
IWD-1220(aXI)
HSC-04 3'
M-230-2 CZ 3
IWD-1220(aXI)
HSC-05 1
M-230-2 CS 3
IWD-1220(a)(1)
HSC-05 1.5 M-230-2 CS 3
IWD-1220(aXI)
HSC-05 3
M 230-2 CS 3
IWD-1220(aXI)
HSC-06 3
M-213-1 RW 3
IWD-1220(a)(1)
HSC-06 2
M-213-2 RW 3
IWD-1220(aXI)
HSC-06 0.75 M-213-2 RW 3
IWD-1220(aXI)
HSC-06 4
M-213-1 RW 3
IWD-1220(aXI)
HSC-07 1.5 M-213-1 RW 3
IWD-1220(aXI) 3-25 Revision 0
ANO Unit 13 Interval Inservice Inspection Plan TABLE 3.1 INSERVICE INSPECTION PIPING LINE LIST (con't)
LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HSC-07 2
M-213-1 RW 3
IWD-1220(a)(1)
HSC-07 3
M-213-1 RW 3
IWD-1220(a)(1)
HSC-10 0.75 M-214-2 LRW 3
IWD-1220(a)(1)
HSC-10 1
M-214-2 LRW 3
IWD-1220(a)(1)
HSC-10 0.5 M-214-2 LRW 3
IWD-1220(a)(1)
HSC-10 0.25 M-214-2 LRW 3
IWD-1220(aXI)
HSC-10 3
M-214-2 LRW 3
IWD-1220(a)(1)
HSC-!l 0.75 M-230-2 SS 3
IWD-1220(a)(I)
HSC-Il 1
M-230-2 SS 3
IWD-1220(a)(1)
HSC-12 1
M-215 GRW 3
IWD-1220(a)(1)
HSC-15 2
M-215 GRW 3
IWD-1220(a)(1)
HSC-16 0.75 M-230-2 RBV 3
IWD-1220(a)(1)
HSC-16 2
M-230-2 RBV 3
IWD-1220(a)(1)
HSC-16 1
M-230-2 RBV 3
IWD-1220(a)(1)
HSC-16 1.5 M-230-2 RBV 3
IWD-1220(a)(1)
IWD-1220(a)(1)
HSC-17 1
M-236 CF 3
HSC-18 0.75 M-214-2 LRW 3
IWD-1220(a)(1)
IISC-18 1
M-214-2 LRW 3
IWD-1220(a)(1)
HSC-19 2
M-215-1 GRW 3
IWD-1220(a)(1) 3-26 Revision 0
l ANO Unit 13"' Interval l
Inservice Inspection Plan l
TABLE 3.1 INSERVICE INSPECTION PIPING LhIE LIST (con't) 1 l LINE SIZE P&ID SYS.
ISI SAFETY EXEMPTION BASIS NO.
(IN)
CLASS FUNCTION HSC-21 1
M-215-1 GRW 3
IWD-1220(aXI)
HSC-21 2
M-215-1 GRW 3
IWD-1220(aXI)
HSC-22 0.5 M-215-1 GRW 3
IWD-1220(aXI)
HSD-21 0.5 M-232-1 SW T3 R,E IWD-1220(aXI) 4 HSD-21 1.5 M-232-1 SW T3 R,E IWD-1220(aXI)
TCD-1 0.5 M-204-3 EFW T3 R
IWD-1220(aXI)
LEGEND AC Reactor Building Chilled Water ILRT Integrated Leak Rate Testing BS Building Spray LRW Liquid Radioactive Waste l
BW Borated Water Storage Tank MS Main Steam BWST Borated Water Storage Tank MU Make Up CAF Reactor Building HVAC N2 Nitrogen CF Core Flood RBHV Reactor Building HVAC CRD Control Rod Drive RBV Letdown Cooler Vent CST Condensate Storage Tank RCP Reactor Coolant Pump CZ Pressurizer ReliefDischarge RCS Reactor Coolant System DHR Decay Heat Removal RW Radioactive Waste EFW Emergency Feed Water SA Sersice Air FP Fire Protection SF Spent Fuel FW Feed Water SMP Sampling GRW Gaseous Rad Waste SS Quench Tank Transfer Pump ICW Intermediate Cooling Water SW Service Water i
3-27 Revision 0
..___.m.
m._
i ANO Unit 13 Interval l
d Inservice Inspection Plan t
SECTION 4.0 -
l INSERVICE INSPECTION
SUMMARY
TABLES l
L i
This section provides a summary listing of all items subject to inservice inspection during the third inspection interval at ANO-1.
4.1 ASME Section XIInservice Insocetions j
t The ASME Section XI Inservice Inspection Summary Table 4.1 provides the following
' information:
l 4.1.1 Examination Category j
a l
1 l
This column lists the examination category as identified in ASME Section XI, l
l Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, and IWF-2500-1. Only those j
examination categories applicable to ANO-1 are identified.
i i
4.1.2 Item Number and Description of Components Examined l
These columns list the item number and description as defined in ASME Section l
l XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, and IWF-2500-1. - Only L
those item numbers applicable to ANO-1 are identified.
i 4.1.3 Number of Components j
i This column lists the population of components potentially subject to examination.
The number of components actually examined during the inspection interval will be
.j L
based upon 'the Code requirements for the subject item number (e.g., 7.5% of i
Examination Category C-F-1, Item Number C5.11 components will be examined during the inspection interval).
l 4.1.4 Examination Method L
The column lists the examination method (s) required by AShE Section XI, Tables IWB-2500-1, IWC-2500-1, IWD-2500-1, and IWF-2500-1.
l 4.1.5 Request Number l
This column provides a listing of applicable Requests for Alternatives or Relief i
Requests. If a request number is identified, see the corresponding Request for Alternative or Relief Request in Section 5.4. This column also lists Requests for Alternatives submitted for all Entergy stations in letter Nos. GNRO-%/00069, 70, l
71, and 72 as described in Section 5.1.2 of this ISI Plan.
4-1 l
Revision 0
d ANO Unit 13 Intenal Inservice Inspection Plan i
I TABLE 4.1 ASME SECTION XI i
INSERVICE INSPECTION
SUMMARY
TABLE i
Examination Item Description of Components Examined Number of Examination Request Category Number Components Method (s)
Number (s)
B-A Bl.11 Circumferential Shell Welds 4
Volumetric l
Pressure Bl.12 Longitudinal Shell Welds 4
Volumetric j
Retaining Bl.21 Circumferential Head Welds 1
Volumetric Welds in Bl.30 Shell-to-Flange Weld 1
Volumetric Reactor B1.40 Head-to-Flange Weld 1
Volumetric &
i Vessel Surface Bl.50 Repair Welds i
Volumetric t
B-B B2.11 Pressurizer Circumferential Shell-to-Head Welds 2
Volumetric Pressure B2.12 Pressurizer Longitudinal Shell-to-Head Welds 3
Volumetric Retaining B2.40 Steam Generator Tube Sheet-to-Head Weld 4
Volumetric 3
Welds in Vessels Other Than Reactor I
Vessels B-D B3.90 Reactor Vessel Nozzle-to-Vessel Welds 8
Volumetric 97-004 f
Full B3.100 Reactor Vessel Nozzle Inside Radius Section 8
Volumetric 97-004 Penetration B3.110 Pressurizer Nozzle-to-Vessel Welds 5
Volumetric
[
Welded B3.120 Pressurizer Nozzle Inside Radius Section 5
Volumetric Nozzles in B3.130 Steam Generator (Primary Side) Nozzle-to-Vessel 6
Volumetric Vessels Welds
[
B3.140 Steam Generator (Primary Side) Inside Radius Section 6
Volumetric L
f 4-2 l
Revision 0
[
- ~. - -
ANO Unit 13 Interval Inservice Inspection Plan TABLE 4.1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
TABLE (cont.)
Examination item Description of Components Examined Number of Examination Request Category Number Components Method (s)
Number (s)
B-F B5.10 Reactor Vessel Dissimilar Metal Nozzle-to-Safe End 2
Volumetric &
96-003' Pressure Butt Welds NPS 4 or Larger Surface 97 rg4 Retaining Dissimilar B5.40 Pressurizer Dissimilar Metal Nozzle-to-Safc End Butt 2
Volumetric &
Metal Welds Welds NPS 4 or Larger Surface in Vessel B5.50 Pressurizer Dissimilar Metal Nozzle-to-Safe End Butt 3
Surface l
Nozzles Welds Less than NPS 4 1
B-G-1 B6.10 Reactor Vessel Closure Head Nuts 60 Visual, VT-1 Pressure B6.20 Reactor Vessel Closure Studs, in Place 60 Volumetric Retaining B6.30 Reactor Vessel Closure Studs, when Removed 60 Volumetric &
Bolting Greater Surface Than 2 in.
B6.40 Threadsin Reactor Vessel Flange 60 Volumetric in Diameter B6.50 Reactor Vessel Closure Washers, Bushings 60 Visual, VT-1 B6.60 Pressurizer Bolts and Studs 1
Volumetric B6.70 Pressurizer Flange Surfaces, When Connection i
Visual VT-1 Disassembled B6.80 Pressurizer Nuts, Bushings, and Washers 1
Visual VT-1 i
B6.180 Pump Bolts & Studs 4
Volumetric B6.190 Pump Flange Surfaces, When Connection 4
Visual, VT-1 Disassembled l
B6.200 Pump Nuts, Bushings, and Washers 4
Visual, VT-1 1
4-3 l
Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 4.1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
TABLE (cont.)
Examination Item Description of Components Examined Number of Examination Request Category Number Components Method (s)
Number (s)
B-G-2 B7.20 Bolts, Studs, & Nuts in the Pressurizer 1
Visual, VT-1 Pressure B7.30 Bolts, Studs, & Nuts in Steam Generators 8
Visual, VT-1 Retaining B7.50 Bolts, Studs, & Nuts in Piping 3
Visual, VT-1 Bolting,2 in.
B7.70 Bolts, Studs, & Nuts in Valves 23 Visual, VT-1
& Less in B7.80 Bolts, Studs, & Nuts in CRD Housings 69 Visual, VT-1 Diameter B-J B9.11 Circumferential Weldsin Piping 142 Volumetric &
96-003' Pressure NPS 4 or Larger Surface Retaining B9.12 Longitudinal Welds in Piping 52 Volumetric &
GNRO-Weldsin NPS 4 or Larger Surface 96/00072 Piping B9.21 Circumferential Weldsin Piping 205 Surface Less than NPS 4 B9.31 Branch Pipe Connection Welds 2
Volumetric &
NPS 4 or Larger Surface B9.32 Branch Pipe Connection Welds 14 Surface Less than NPS 4 B9.40 Socket Welds 29 Surface 2
2 B-K B10.10 Integrally Welded Attachments to Vessels 21 Surface GNRO-Integral 96/00070 2
Attachments B10.20 Integrally Welded Attachments to Piping 1
Surface GNRO-for Class 1 96/00070
- Vessels, Piping, Pumps l
& Valves 4
4-4 Revision 0
m_.
d ANO Unit 13 Interval-Inservice Inspection Plan TABLE 4.1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
TABLE (cont.)
Examination Item Description of Components Examined Nnmber of Examination Request Category Number Components Method (s)
Number (s)
B-L-1 B12.10 Pump Casing Welds 12 Volumetric Pump Casing Welds B-L-2 B12.20 Pump Casings 4
Visual, VT-3 Pump Casings B-M-1 B12.40 Valve Body Welds in Valves NPS 4 or Larger 4
Volumetric Valve Body Welds B-M-2 B12.50 Valve Bodies, Exceeding NPS 4 10 Visual, VT-3 Valve Bodies i
B-N-1 B13.10 VesselInterior 1
Visual, VT-3 Interior of Reactor Vessel B-N-2 B13.50 Interior Attachments within Beltline Region in 1
Visual VT-1 Integrally Reactor Vessel l
Welded Core B13.60 Interior Attachments beyond Beltline Region in i
Visual, VT-3 l
Support Reactor Vessel Stmetures &
L Interior Attachments to I
Reactor Vessels Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 4.1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
TABLE (cont.)
Examination Item
. Description of Components Examined Number of Examination Request Category Number Components Method (s)
Number (s)
B-N-3 B13.70 Core Support Structure in Reactor Vessel 1
Visual, VT-3 Removable Core Support Structures B-O B14.10 Weldsin CRD Housing 69 Total Volumetric or Pressure (24 Surface Retaining Peripheral)
Welds in Control Rod Housings B-P B15.10 RPV - System Leakage Test i
Visual, VT-2 97-005 All Pressure B15.20 Pressurizer-System Leakage Test i
Visual, VT-2 97-005 Retaining B15.30 Steam Generator - System Leakage Test 2
Visual, VT-2 97-005 Components B15.50 Piping - System Leakage Test See Note 3 Visual, VT-2 97-005 (Class 1)
B15.60 Pumps - System Leakage Test See Note 3 V;sual, VT-2 97-005 B15.70 Valves - System Leakage Test See Note 3 Visual, VT-2 97-005 B-Q B16.10 Steam Generator Tubing in Straight Tube Design 2
Volumetric
- Steam Generator Tubing 4-6 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan t
TABLE 4.1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
TABLE (cont.)
Examination Item Description of Components Examined Number of Examination Request Categen Number Components Method (s)
Number (s)
C-A Cl.10 Shell Circumferential Welds 8
Volumetric Pressure Cl.20 Head Circumferential Welds 2
Volumetric Retaining Cl.30 Tubesheet-to-Shell Welds 6
Volumetric Welds in Pressure Vessels C-B C2.11 Nozzle-to-Shell (or Head) Weld in Vessels < 1/2" 6
Surface Pressure Nominal Thickness Retaining C2.21 Nozzle-to-Shell (or Head) Weld without Reinforcing 4
Volumetric &
Nozzle Welds Plate in Vessels > 1/2" Nominal Thickness Surface in Vessels C2.22 Nozzle Inside Radius Section 4
Volumetric C-C C3.10' Integrally Welded Attachments to Pressure Vessels 20 Surface GNRO-2 Integral 96/00070 Attachments C3.20' Integrally Welded Attachments to Piping 102 Surface GNRO-for Class 2 96/00070
- Vessels, Piping, Pumps and Valves i
4-7 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan TABLE 4.1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
TABLE (cont.)
6 Examination Item Description of Components Examined Number of Examination Request Category Number Components Method (s)
Number (s)
C-F-1 C5.11 Circumferential Welds in Austenitic Stainless Steel or 467' Volumetric &
97-003 Pressure High Alloy Piping 2 3/8" Nominal Wall Thickness for Surface Retaining Piping > NPS 4 Welds in C5.12 Longitudinal Welds in Austenitic Stainless Steel or 35' Volumetric &
97-003, Austenitic High Allow Piping 2 3/8" Nominal Wall Thickness for Surface GNRO-l Stainless Steel Piping > NPS 4 96/00072 orHigh Alloy C5.21 Circumferential Welds in Austenitic Stainless Steel or 665 Volumetric &
97-003 Piping High Alloy Piping 21/5" in. Nominal Wall Thickness Surface for Piping 2 NPS 2 and s;NPS 4 5
C-F-2 C5.51 Circumferential Welds in Carbon or Low Alloy Steel 193 Volumetric &
Pressure Piping 2 3/8" Nominal Wall Thickness for Piping Surface L
Retaining
> NFS 4 Welds in C5.81 Circumitzential Welds in Carbon or Low Alloy Steel 18 Surface Carbon or Low Pipe Brarxh Connections of Branch Piping 2 NPS 2 l
Alloy Steel Piping C-H C7.10 Pressure Vessels - System Pressure Test See Note 3 Visual, VT-2 97-005 All Pressure C7.30 Piping - System Pressure Test See Note 3 Visual, VT-2 97-005 Retaining C7.50 Pumps - System Pressure Test See Note 3 Visual, VT-2 97-005 Components C7.70 Valves - System Pressure Test See Note 3 Visual, VT-2 97-005 (Class 2) i 4-8 Revision 0
... -. _ ~
ANO Unit 13"' Interval Inservice Inspection Plan TABLE 4.1 ASME SECTION XI INSERVICE INSPECTION
SUMMARY
TABLE (cont.)
Examination Item Description of Components Examined Number of Examination Request Category Number Components Method (s)
Number (s) 2 2
D-A D1.20' Integrally Welded Attachments to Piping 75 Visual, VT-1 GNRO-96/00070.;
Integral 2
Attachments DI.30' Integrally Welded Attachments to Pumps 2
Visual, VT-1 GNP.0-for Class 3 96/00070
- Vessels, Piping, Pumps
& Valves D-B D2.10 Pressure Vessels - System Leakage Test See Note 3 Visual, VT-2 All Pressure D2.20 Pressure Vessels - System Hydrostatic Test' See Note 3 Visual, VT-2 See Note 6 Retaining D2.30 Piping - System Leakage Test See Note 3 Visual, VT-2 Components D2.40 Piping - Svstem Hydrostatic Test' See Note 3 Visual, VT-2 See Note 6 (Class 3)
D2.50 Pumps - System Leakage Test See Note 3 Visual, VT-2 D2.60 Pumps - System Hydrostatic Test' See Note 3 Visual, VT-2 See Note 6 D2.70 Valves - System Leakage Test See Note 3 Visual, VT-2 D2.80 Valves - System Hydrostatic Test' See Note 3 Visual, VT-2 See Note 6 F-A Fl.10' Class 1 Piping Supports 94 Visual, VT-3 7
Supports Fl.20' Class 2 Piping Supports 376 Visual, VT-3 Fl.30' Class 3 Piping Supports 379 Visual, VT 3 F1.40' Supports Other Than Piping Supports 30 Visual, VT-3 (Class 1,2, and 3) i 4-9 Revision 0
d ANO Unit 13 Interval Inservice Inspection Plan Notes:
1.
Request for Alternative 96-003 has been transmitted to the NRC le a separate subnuttal (ICAN069703) and therefore is not included in this ISI Plan.
2.
The Examination Categories, Item Numbers and Examination methods used for the inservice inspection of integrally welded attachments are in accordance with Code Case N-509 (request for alternative submitted in letter No. GNRO-96/00070).
3.
Pressure retaining components (e.g., pressure vessels, pumps, valves, piping, etc.) that are subject to system pressure or hydrostatic tests are those components within the systems identified in the Piping and Instrumentation Drawings listed in Table 2.2 of this ISI Plan.
~
The extent, frequency and acceptance standards for the exam' ation of Steam Generator tubing will be in acwidance with 4.
m ANO-1 Technical Specification 4.18.
5.
The number of Class 2 piping welds identified in Table 4.1 includes those welds in piping < 3/8" nominal wall thickness in accordance with Note 2 ofTable IWC-2500-1, Examination Categories C-F-1 and C-F-2.
6.
The Class 3 system hydrostatic pressure tests will be performed to the alternate rules for 10-year hydrostatic pressure testing delineated in Code Case N-498-1. See Section 5.1.2 of this ISI Plan for details.
7.
Snubber assemblies will be tested and inspected in accordance with ANO-1 Technical Specification 4.16.
8.
Individual supports are further classified by support types which are identified by a single letter suffix to the Code Item Number.
The following suffixes are used at ANO-1:
CODE ITEM SUPPORT TYPE SUFFIX A
1-Way Restraint B
Muhi-Directional Restraint i
C Variable Spring D
Constant Force Spring Hanger i
E Anchor i
F Snubber G
Whip Restraint H
Other-Guide I
Other-Grout J
0;her i
~
4-10 i
Revision 0
[
d ANO Unit 13 Interval Inservice Inspection Plan j
SECTION 5.0 ALTERNATIVE REOUIREMENTS TO ASME SECTION XI:
1992 EDITION WITH PRESSURE TESTING CRITERIA FROM THE 1993 ADDENDA This section lists the alternative requirements to ASME Section XI,1992 Edition with portions of the 1993 Addenda, being adopted for the third interval inservice inspection program at j
ANO-1. The alternative requirements presented are in accordance with ASME Section XI and 10CFR50.55a, as applicable.
5.1 Adoption of Code Cases
]
This section addresses the adoption of Code Cases during the third inservice inspection interval at ANO-1. Code Cases adopted for inservice inspection use during the third interval are listed in Tables 5.1 and 5.2 of this Inservice Inspection Plan. In all cases, the use and adoption of Code Cases will be in accordance with ASME Section XI, IWA-2440 and 10CFR50.55a. The methodology for adopting Code Cases is divided into the four categories clarified below.
I 5.1.1 Adoptio 1 of Code Cases Listed for Generic Use in Regulatory Guide 1.147 Code Cases that are listed for generic use in Regulatory Guide 1.147, Revision 11 and later, are adopted for use during the third inservice inspection interval by inclusion in Table 5.1 of this Inservice Inspection Plan.
All conditions or limitations delineated in Regulatory Guide 1.147 for a particular Code Case apply.
]
TABLE 5.1 LIST OF ADOPTED CODE CASES CODE REG. GUIDE DATE CASE TITLE 1.147 ADOPTED NUMBER REVISION N-435-1 Alternative Examination Requirements for 11 6/1/97 Vessels with Wall Thickness 2 in. or Less i
N-460 Alternative Examination Coverage for 11 6/1/97 Class 1 and 2 Welds N-461 Alternative Rules for Piping Calibration 11 6/1/97 Block Thickness N-481 Alternative Examination Requirements for 11 6/1/97 i
Cast Austenitic Pump Casings l
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5.1.2 Adoption of Code Cases Not Listed for Generic Use in Regulatory Guide 1.147 Adoption of Code Cases that have been approved by the Board of Nuclear Codes and Standards, but that have not been listed for generic use in Regulatory Guide 1.147, may be submitted in the form of a Request for Alternative in accordance with 10CFR50.55a(a)(3). In addition to the requirements stated in the Code Cases, criteria may be stipulated in the Request for Alternative or may be agreed upon through subsequent correspondence with the NRC. Once approved, these Requests for Alternatives will be available for use at ANO-1 until such time that i
the Code Cases are adopted into Regulatory Guide 1.147. Once added into i
Regulatory Guide 1.147, any stipulated conditions for use will be followed, per Section 5.1.1 of this ISI Plan.
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Table 5.2 lists those Code Cases which have been previously submitted to the NRC for approval to use at ANO-1. Requests for Alternatives for the Code Cases listed in the table were submitted by Entergy Operations, Inc. in letter i
numbers GNRO-96/00069, 70, 71, and 72, all dated June 20, 1996. Two additional Code. Cases were submitted for review and approval by correspondence dated June 23,1997 (ICAN069704). Requests to use Code Cases N-521 and N-533 are attached to this submittal. Hydrostatic testing l
requirements equivalent to those in Code Case N-498-1 were approved for use in j
the NRC letter dated December 12,1996 (0CNAl29613),
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Inservice Inspection Plan TABLE 5.2 CODE CASES SUBMITTED THROUGH REQUESTS FOR ALTERNATIVES CODE CASE TITLE LETTER NUMBER NUMBER N-416-1 Alternative Pressure Test Requirement for Welded ICAN069704
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l Repairs or Installation of Replacement Items by Welding, Class 1,2 and 3 r
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N-508-1 Rotation of Serviced Snubbers and Pressure Relief GNRO-Valves for the Purposes ofTesting 96/00071 N-509 Alternative Rules for the Selection and GNRO-l Examination of Class 1,2 and 3 Integrally Welded 96/00070 Attachments l
N-521 Alternate Rules for the Deferral ofInspections on Attached Nozzle-to-Vessel Welds, Inside Radius Sections and Nozzle-to-Safe End Welds of the Reactor Vessel i
N-524 Alternative Examination Requirements for GNRO-l Longitudinal Welds in Class 1 and 2 Piping 96/00069 i
l N-532 Alternative Requirements to Repair and ICAN069704 Replacement Requirements and Inservice Summary Report Preparation and Submission as Required byIWA-4000 and IWA-6000 I
N-533 Alternate Rules for Insulation Removal During Attached IWB-5000 and IWC-5000 Pressure Tests at Bolted Connections in Systems Borated for the Purpose of Controlling Reactivity N-546 Alternative Requirements for Qualification of VT-GNRO-2 Examination Personnel 96/00072 I
l 5.1.3 Adoption of Code Cases Listed for Generic Use in Regulatory Guide 1.147 But Subsequently Annulled by ASME Section XI l
Under cenain circumstances, it may be necessary to adopt a Code Case that has been listed for generic use in Regulatory Guide 1.147, but subsequently annulled by ASME Section XI. Therefore, Entergy Operations endorns all revisions of 5-3 l
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d ANO Unit 13 Interval Inservice Inspection Plan Regulatory Guide 1.147. from Revision 11 up to and including the most recent revision. Endorsement of these revisions of Regulatory Guide 1.147 does not
' commit Entergy Operations to all the Code Cases listed therein, but rather allows
- for - selection of a previously accepted Code Case. - The purpose of this endorsement is to identify all Code Cases that could potentially be incorporated into the Inservice Inspection Plan in accordance with IWA-2441.
5.1.4 Adoption of Code' Cases Issued Subsequent to Filing this Inservice Inspection -
Plan Code Cases issued-by ASME Section XI subsequent to filing this Inservice Inspection Plan will be proposed for use in amendments to this Plan in accordance with ASME Section XI, IWA-2441(d).
Entergy Operations intends to submit a request to use the alternative criteria of ASME Code Case N-560, " Alternative Examination Requirements for Class 1, Category B-J Piping Welds." Entergy Operations is participating in a pilot study for this Code Case which is due to be completed prior to the first refueling outage in the third inservice inspection interval. Since the results of the Code Case pilot study are not available at this time, no Examination Category B-J welds will be inspected prior to the submittal of a Request for Alternative based on Code Case N-560. If this Request for Alternative is not available in time for the first refueling outage, alternative criteria will be submitted to the Nuclear Regulatory -
Commission which will be based on the 1992 Edition of ASME Section XI, with provisions to-address the selection criteria stated in Table IWB-2500-1, Examination Category B-J, Footnote (1)(b).
5.2 Use of Subseauent Editions of ASME Section XI In accordance with 10CFR50.55a(g)(3)(iv), components (hduding supports) may meet the requirements set forth in subsequent editions of Codes ed Addenda, or portions thereof, which are incorporated by reference in 10CFR50.55a(b), subject to the limitations and modifications listed therein. This Section of the Inservice Iny ction Plan provides for alternative requirements from approved subsequent Code editions that may be adopted during the third inservice inspection interval. This Inservice Inspection Plan will be amerded periodically for adoption of subsequent Code rules.
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l ANO Unit 13'd Interval Inservice Inspection Plan 5.3 Inservice Inspection Reavest for Alternative and RelierRequest index l
This section provides a summary listing of all Requests for Alternatives and Relief Requests related to inservice inspections at ANO-1 other than the previously listed Code Cases.
TABLE 5.3 INSERVICE INSPECTION REQUEST FOR ALTERNATIVES AND RELIEF REQUEST INDEX Request Submittal Topic No.
Date 96-003 6/16/97 Examination of Class 1 Welds in Reactor Pressure Vessel Nozzles and Safe Ends97-003 Attached Examination of Class 2 Welds in Piping Less than 3/8 in. Nominal Wall Thickness Inservice Inspection Reauests for Alternatives and Relief Reauests 5.4 5.4.1 Alternatives to Code required examinations may be authorized by the NRC, as I
allowed by 10CFR50.55a(a)(3), provided that design, fabrication, installation, testing and inspection performed in compliance with Codes and Section XI requirements would result in hardship without a compensating increase in the level of quality and safety, or provided that the proposed alternative examination will assure an acceptable level of quality and safety. Specific exceptions shall be documented in the form of a Request for Alternative and included in this Section, as applicable.
5.4.2 This Section shall include Relief Requests written in accordance with 10CFR50.55a(g)(5) when specific ASME Section XI requirements for inservice inspection are considered impractical.
If examination requirements are determined to be impractical during the course of the interval, relief requests shall j
be subtaitted in accordance with 10CFR50.55a(g)(5).
5.4.3 Relief Requests for incomplete examinations shall be submitted in accordance with 10CFR50.55a(g)(5)(iv) throughout the interval as limitations are identified.
Due to ongoing changes in nondestructive examination procedures, techniques and requirements, it is considered that submitting Relief Requests for incomplete examinations when they are evaluated will provide a more accurate representation of the limitations.
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e ANO Unit 13 Interval Inservice Inspection Plan REOUEST NUMBER: 97-003 (Page1of3)
COMPONENTIDENTIFICATION Code Class:
2
Reference:
IWC-1220, IWC-2500, Table IWC-2500 1 Examination Category:
C-F-1 Item Numbers:
C5.11, C5.12, C5.21 i
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Description:==
Examination of Class 2 Welds in Piping Less than 3/8 in. Nominal Wall Thickness Component Numbers:
All Class 2 Austenitic Stainless Steel Piping Welds CODE REOUIREMENT ASME Section XI, Table IWC-2500, Examination Category C-F-1, Note (2) states the following:
The welds selected for examination shall include 7.5%, but not less than 28 welds, of all austenitic stainless steel or high alloy welds not exempted by IWC-1220. (Some welds not exempted by IWC-1220 are not required to be nondestmctively examined per Examination Category C-F-1. These welds, however, shall be included in the total weld count to which the 7.5% sampling rate is applied.) The examinations shall be distributed as follows:
(a) the examinations shall be distributed among the Class 2 systems prorated, to th-degree practicable, on the number of:anexempt austenitic stainless steel or high alloy welds in each system (i.e., if a system contains 30% of the nonexempt welds, then 30% of the nondestmetive examinations required by Examination Category C-F-1 should be performed on that system);
(b) within a system, the examinations shall be distributed among terminal ends and stmetural discontinuities prorated, to the degree practicable, on the number of nonexempt terminal ends and stmetural discontinuities in that system; and (c) within each system, examinations shall be distributed between line sizes prorated to the degree practicable.
- BASIS FOR ALTERNATIVE l
Pursuant to 10CFR50.55a(a)(3)(i), an altemative is requested on the basis that it provides an acceptable level of quality and safety.
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BASIS FOR ALTERNATIVE (coni) i
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Code rules require that a 7.5% sampling rate be applied to all Examination Category C-F-1 piping welds not exempted by IWC-1220. The total weld count to which the sampling rate is l
applied includes both those welds required to be examined (i.e., 2 3/8" nominal wall thickness) l and those welds for which examination is not required (i.e., < 3/8" nominal wall thickness). The j
total number ofwelds required to be examined are then distributed, in a prorated manner, among l
those systems requiring examination. Those piping welds less than 3/8" nominal wall thickness, i
while not requiring examination, will have an impact on the number of examinations required m i
systems with piping 2 3/8" nominal wall thickness.
l At ANO-1 a number of the Class 2 systems have pipmg with nominai wall thickness < 3/8". This includes portions of the Make-up, Decay Heat Removal, Low Pressure Injection and Building i
I Spray systems. In the past, the Nuclear Regulatory Commission has expressed concerns at a j
number of nuclear facilities, including ANO-2, about examinations not being performed on j
i sections of piping because they were less than 3/8" nominal wall thickness.
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In addition to this issue, most of the same Class 2 stainless steel piping is subject to the i
commitments made in response to Nuclear Regulatory Commission IE Bulletin 79-17, which j
, stipulates examination. of pipes susceptible to cracking from stagnant borated systems in j
Pressurized Water Reactors.- The purpose of this Request is to propose alternative examination j
i requirements for Class 2 piping which addresses both the " thin wall piping" and the IE Bulletin l
79-17 issues.
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Based on the reasons listed below, the proposed alternative examinations will ensure that an l
acceptable les el of quality and safety will be met.
- 1) Applying a sampling rate of 7.5% to all Examination Category C-F-1 piping welds regardless of wall thickness will ensure that all Class 2 systems will undergo l
examinations.
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- 2) During the second ten year interval at ANO-1 piping that was originally subject to IE i
Bulletin 79-17, but not the ASME Code, was upgraded to Class T2 (i.e., treated as 2
Class 2 for inspection and testing purposes). Therefore, this piping is included in the sampling plan and subject to examination.
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BASIS FOR ALTERNATIVE (con't)
- 3) Intergranular Stress Corrosion Cracking (IGSCC) in Class 2 piping is not the i
significant concern that it was in 1979. Since IE Bulletin 79-17 was first issued, l
numerous examinations have been performed. In addition, the cause of the cracking 1 i
which was the introduction of sodium thiosulfate, has long since been temoved. his j
logical to conclude that welds that have not shown signs of cracking thus far would i
remain defect-free because there is no longer a degradation mechanism to initiate or propagate flaws.
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- 4) The examinations stipulated are conservative, but appropriate.
Volumetric i
examinations are specified on piping which could be susceptible to IGSCC because they are more appropriate than surface examinations for detecting cracking initiating from the inside surface of the pipe. However, even IE Bulletin 79-17 doesn't require volumetric examinations on piping less than 0.250" thick.
PROPOSED ALTERNATE EXAMINATIONS A uniform 7.5% sampling rate will be applied to all Examination Category C-F-1 piping welds regardless of nominal wall thickness. The examination requirements shall be as follo'ws:
- 1) Piping > 3/8" thick will be subject to volumetric and surface examinations as stated in ASME Section XI.
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- 2) Piping < 3/8" thick which is not subject to IE Bulletin 79-17 will be subject to a surface examination.
- 3) Piping < 3/8" thick which is subject to IE Bulletin 79-17 will be subject to a volumetric examination.
i Systems considered subject to IE Bulletin 79-17 will be those that meet the definition of a
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" stagnant, oxygenated, borated water system," as stated in the bulletin.
The piping welds selected for examination will still be subject to the distribution requirements stated in ASME Section XI, Table IWC-2500-1, Examination Category C-F-1, Note (2).
APPLICABLE TIME PERIOD Application of the attemative criteria is requested for the third ten-year interval of the Inservice Inspection Program for ANO-1, which began on June 1,1997.
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REOUEST NUMBER: 97-004 l
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COMPONENTIDENTIFICATION Code Class:
1
References:
IWB-2500, Table IWB-2500-1 Code Case N-521 Examination Categories:
B-D, B-F l
Item Numbers:
B3.90, B3.100, B5.10
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Description:==
Alternate Rules for the Deferral of Inspections on Nozzle-to-l Vessel Welds, Inside Radius Sections and Nozzle-to-Safe End i
Welds of the Reactor Vessel i
Component Numbers:
Nozzle-to-Vessel Welds (Item No. B3.90)
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01-011 01-012 i
01-013 l
01-014 i
01-015 i
01-016 01-017 01-018 Inner Radius Sections (Item No. B3.100) 01-011R 01-012R 01-013R I
01-014R 01-015R 01-016R 01-017R 01-018R Nozzle-to-Safe End Welds (Item No. BS.10)01-025 01-026 1
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CODE REOUIREMENTS ASME Section XI, Table IWB-2500-1, Examination Category B-D requires volumetric examination of reactor vessel nozzle-to-vessel welds and their inside radius sections once each ten-year inspection interval. Note (2) of Examination Category B-D states that at least 25 1
percent, but not more than 50 percent (credited), of the reactor vessel nozzles shall be examined by the end of the first inspection period, and the remainder by the end of the inspection interval.
Table IWB-2500-1, Examination Category B-F, Note (1) states that the reactor vessel nozzle-to-safe end weld examinations may be performed coincident with the vessel nozzle examinations required by Examination Category B-D.
BASIS FOR ALTERNATIVE Pursuant to 10CFR50.55a(a)(3)0i), an alternative is requested on the basis that the original requirements would result in hardship without a compensating increase in the level of quality and safety.
Reliefis requested to defer 100 percent of the reactor vessel nozzlo-to-vessel weld examinations, the nozzle inside radius section examinations, and the nozzle-to~ safe end weld examinations to the third period of the third ten-year inspection interval at ANO-J.
Entergy Operations believes that performing 25 percent to 50 percent of the reactor vessel nozzle examinations in the first period of the third inspection interval is impractical for the following reasons:
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- 1) The vendor cost (not including site training, plant support, or potential critical path time) to perform these examinations with automated tooling in the first inspection period is currently estimated at $250,000. The cost to perform these same examinations at the end of the third inspection interval concurrent with the reactor vessel tea-year examination is estimated at only $25,000. The major expense associated with the first inspection period examinations is the added equipment and personnel mobilization costs and equipment assembly and disassembly costs.
- 2) Approximately three to four man-rem exposure is currently expended for automated
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equipment assembly and disassembly in the reactor cavity area. In addition to exposure, l
there are approximately two to three cubic feet of solid radwaste generated during 1
performance of automated examinations in the reactor vessel. Under current Code mies, this personnel exposure and radwaste generation would be incurred twice; once for the nozzle first inspection period examinations and again for the reactor vessel examinations at the end of the inspection interval. Performing the nozzle examinations concurrent with the reactor i
vessel ten-year examinations will save approximately three to four man-rem exposure and two to three cubic feet of solid radwaste.
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-l BASIS FON ALTERNATIV,6(coni)
For reasons listed below, Entergy Operations believes that deferral of 100 percent of the reactor l
vessel nozzle examinations to the end of the third inspection interval wih provide an acceptable t
level of safety and quality.
- 1) All Reactor Vessel nozzle-to-vessel welds, nozzle inside radius sections, and nozzle-to-safe -
end welds were eumined in 1995 during the third period of the :econd ten-year inspection l
interval. No indications or relevant conditions were discovered that required successive inspections in accordance with Paragraph IWB-2420(b). Furthermore, no inservice repairs i
L or replacements by weldina have ever been performed on any of the nozzle-to-vessel welds, nozzle inside radius sectiors, or nozzle-to-safe end welds at ANO-1.
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- 2) The pressurizer and primary steam generatcr nezzle-to-vessel welds, inside radius sections, and nozzle-to-safe end welds are similar in configuration, material properties, weld process parameters, and operate in the same reactor coolant system environment as the reactor vessel i
nozzles. Due to this similarity, distribution of the pressurizer and steam generator nozzle
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examinations in accordance with Examination Category B-D and Exr cilation Category B-F will further substantiate the integrity of the reactor vessel nozzles until, :cy are examined at or near the end of the third inservice inspection interval.
- 3) Performing all the automated reactor vessel examinations during a single refueling outage improves consistency of the examinations by utilizing the same equ:.pment, personnel, and 1
procedrres. Moreover, this improves the reliability and reproducibility cif the examinations.
PROPO3ED ALTERNATE EXAMINATION Entergy Operations shall complete the required nozzle-to-vessel weld examinations, the nozzle inside radius section examinations, and the nozzle-to-safe end weld examinations concurrent with the reactor vessel ten-year examinations during the third period of the third ten-year inservice inspection interval, in accordance with Code Case N-521.
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APPLICABLE TIME PERIOD Application of the ahernative criteria is requested for the third ten-year interval of the Inservice Inspection Program for ANO-1, which began on June 1,1997 l
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REOUEST NUMBER: 97-00f[
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COMPONENTIDENTIFICA'I10N Code Classes-1 rad 2 i
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References:
P/A-5242(a).
j, Code Case N-533 4
Examination Categories:
B-P and C-H l
. Item Numbers:
B15.10, B15.20, B15.30, B15.40, B15.50, B15.60,' B15.70, j
C7.10, C7.30, C7.50, C7.70 1
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Description:==
Alternate Rules for Insulation Removal During IWB-5000 and j
IWC-5000 Pressure Tests at Bolted Connections in Systems i
l Borated for the Purpose of Controlling Reactivity j
l Component Numbers:
Bolted Connections in Systems Borated for the Purpose of
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Controlling Reactivity I
CODE REQUIREMENT IWA-5242(a) states "For systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure retaining bolted connections for visual examination VT-2."
BASIS FOR ALTERNATIVE
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Pursuant to 10CFR50.55a(s)(3)(ii), an ahernative is requested on the basis that the original requirements would result in hardship without a compe= ting increase in the level of quality and safety.
Systems which are borated for the purpose of controlling reactivity at ANO-1 include reactor coolant, decay heat removal, high pressure injection and make-up. These systems encompass a large portion of the overall ISI program' and physically cover a large expanse of the reactor
- building. Many areas in which this piping and the associated bolted connections are located are difficult to access (e.g., scaffold and /or ladder installation is required) and many of these areu are located such that significant radiation exposures would be encountered.-
j In order to identify leakage to be repaired during the outage, the preferred time frame to perform this inspection is in the beginning of the outage subsequent to depressurization of the reactor j
coolant system. To perform these inspections at pressure would invohe holding the reactor coolant cystem at operating pressure and temperature for an extended petiod of time to allow for scaffold constmetion, insulation remo val ec.id VT-2 inspection.
This is normally a relatively short time frame when the unit is trantitioning to cold shutdown.
Holding the unit at normal operating te aperature and pressure for at. extended period of time would result in a signi6 cant delay in going to cold shutdown.
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REOUEST NUMBER: 97-005 (Page 2 of 3)
BASIS FOR ALERNATIVE (con't) i i
Performing this insper. tion at the end of the outage would be ineffective, since finding leakage at that time would copetitute bringing the unit back to cold shutdown to perform the repair and
' then beginning the start up process over again. Also, in order to reinsalate the reactor coolant i
system at the end of the outage, the unit would have to remain at hot standby while the insulation i
is reinstalled and the scaffolding is removed. Typically, the reinstallation of insulation and removal of scaffolding is performed prior to leaving cold shutdown.
.In addition, the removal and reinstallation of insulation with plant equipment in operation at
-system pressure and temperature increases the risk of personnel injury and presents a safety j'
- concern to plant personnel. The personnel risk and radiation exposure is significant for the removal and reinstallation of insulation at these bolted connections during pressure testing activities.
A VT-2 visual examination with the system depressurized would still provide adequate detection ofleakage because boric acid residue can be easily detected with insulation removed at the bolted i-connection.
l Based on the previously stated reasons, Entergy Operations requests relief from the inspection at operating pressure requirements detailed in IWA-5242(a). In lieu of these requirements, Entergy Operations proposes the alternative examination requirements that follow.
PROPOSED ALTERNATIVE EXAMINATION
- A system pressure test with a minimum four hour hold time and VT-2 visual examination shall be performed each refueling outage without the removal ofinsulation on systems borated for the j
q purpose ofcontrolling reactivity.
i Each refueling outage, the insulation shall be removed from the bolted connections in systems i
borated for the purpose of controlling reactivity, and a VT-2 visual examination shall be performed on each of the connections. During this VT-2 examination, the connections are not required to be pressurized. Any evidence ofleakage shall be evaluated in accordance with IWA-5250.
4 These alternative examination requirements are the same as those specified in ASME Section XI Code Case N-533 as approved by the Board ofNuclear Codes and Standards, with the additional four hour hold time provision stated above.
L These alternatives provide reasonable assurance that safety and integrity will be maintained for bolted connections in systems borated for the purpose of controlling reactivity.
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REOUEST NUMBER: 97-005 l
(Page 3 of 3) j APPLICABLE TIME PERIOD 1
Application of the altemative criteria is requested for the third ten-year interval of the Inaervice Inspection Program for ANO-1, which began on Jane 1,1997.
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