ML20096B379
| ML20096B379 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/22/1983 |
| From: | Ahmed A NUCLEAR ENERGY SERVICES, INC. |
| To: | |
| Shared Package | |
| ML20096B369 | List: |
| References | |
| 80A4420, NUDOCS 8409040127 | |
| Download: ML20096B379 (30) | |
Text
mur DOCUMENT NO.
80A4420 REV y 5 I
30 NUCLEAR ENERGY SERVICES, INC.
PAGE np
=
PSI PROGRAM PLAN:
GENERAL REFERENCE TdXT PERRY NUCLEAR POWER PLANT, UNIT 1 Prepared For CLEVELAND ELECTRIC ILLUM'NATING COMPANY CONTROLLED COPY um om as sw is a r
Troject Appikation Prepared OY Date g APP ROV ALS~
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, S I O N A 1, U R E DATE 151 Prograrns Eng. Mgr.
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80A4420 REVISION LOG ggg PAGE OF,,
NUCLEAR ENERGY SERVICES,INC, RE.
DATE DESCRIPTION APPROVAL go d
d 6/15/81 CRA No.1899 g
d 12/2/83'-
Addition of Component Examinations 1
w r CRA No. 3754 b
d 4/26/84 Per Customer commento. All pages.
CRA #4189.
b 8/21/84 Correction of page numbers 9, 10, 11, 12, v
13 and 14, CRA 4572 db 5
8/22/84 5
CRA No. 4578 Por Custoror comments s
v
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eer OM
r OA%20 DOCUMENT NO.
PAGE OF NUCLEAR ENERGY SERVICES, INC.
TABLE OF CONTENTS PAGE b
1.
INTRODUCTION 4
2.
BASES FOR PRESERVICE INSPECTION PROGRAM 5
2.1 NRC Regulations 5
2.2 Definition of Owner Intent 5
4 3.
PRESERVICE INSPECTION PROGRAM PLAN DESCRIPTION 6
3.1 Document Designations 6
3.2 Zone Designations 8
Zone Figures 8
l 3.3 Exceptions 15 3.4 Exemptions 15 3.4.1 Quality Group A 15 3.4.2 Quality Group B 15 3.4.3 Quality Group A, Group B, and Group C 16 3.4.4 Exempt Components 16 3.5 Quality Assurance 16 3.6 Examination Procedures 17 3.7 Ultrasonic Testing Calibration Standards 17 3.8 Evaluation Criteria 22 3.9 Records and Reports 22 3.10 Personnel Qualification Requirements 22 3.11 Pre-examination Requirements 22 3.12 Piping System Documents 23 3.13 Valve and Pump Grouping 27 l
LET OF TABLES 3.1 Program Plan and System Documents 6
3.2 General Reference Documents 7
3.3 Zone Figures 3
3.4 Reference NDE Procedures 19 l
3.5 Progran. Plan Calibration Standards 20 i
3.6 Designations 25 3.7 Pump-Valve Grouping 27 FORM a NES 205 2/80
80A4420 DOCUMENT NO.
allir PAGE OF NUCLEAR ENERGY SERVK;ES. lNC.
- 1. INTRODUCTION This Program Plan has been prepared to fulfill the Preservice Inspection (PSI) requirements for the nuclear system compone'nts of Perry Nuclear Power Plant, Unit 1, owned by the Clevelar.d Electric illuminating Company. This Program Plan will also be written to meet any Augmented Inspection requirements committed to by Cleveland Electric Illuminating Company. These' PSI requirements are specified by the Code of Federal Regulations,10 CFR 50.55 a(g).
The scope of examinations include Reactor Pressure Vessel (RPV), and Pressure Vessels, piping, components and their supports of the Reactor Coolant Pressure Boundary, as classified for Inservice Inspection (ISI). Systems or portions of systems b
common to Units 1 and 2 will be indentified in this Program Plan Unit 1.
The scope of examinations (as delineated above), procedures, and acceptance criteria meet the requirements outlined in Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (BPV) Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1977 Edition with Addenda through Summer 1978. The extent of examination is determined by requirements of Addenda through Summer 1975 of Category B-3 for Class I pipe welds; of Categories C-F and C-G for Class 2 pipe welds of the Residual Heat Removal System, Emergency Core Cooling Systems, and Containment Heat Removal System; and of Categories C-F and C-G for other Class 2 System pipe welds. Component supports will be examined in accordance with subsection IWF to the edition with latest approved addenda of the d
code.
This PSI Program Plan presents information in a general text for overall performance of examinations. Examinations for individual piping systems are listed in system PSI Programs, each of which is a separate document. These piping system documents itemize the system-srMtic examinations.
The examinations shall comply with Section XI requirement: of examination categories, methods, techniques, and procedures; of personnel qualifications; of documentation, mapping, and evaluation of inspection results; and of disposition and repair.
FORM # NES 205 2/80
ai.
o 80A4420 DOCUMENT NO.
my 5
30 PAGE op NUCLEAR ENERGY SERVICES. INC.
s The Program Plan discusses the regulatory requirements comprising the bases of the development of the plan and the technical scope of examinations to satisfy these requirements.
The program plan also presents procedures for performance and documentation of these examinations.
- 2. BASES FOR PRESERVICE INSPECTION PROGRAM 2.1 NRC REGULATIONS b
Title 10 of the Code of Federal Regulations, Part 50, Subsection 50.55 (a) establishes the edition of Section XI of the ASME BPV Code applicable to Preservice Inspection of the Balance of Plant based upon the date of construction permit. This unit is required to comply with rer sirements set forth in ASME Code no earlier than Summer 1972 Addenda i i the 1971 edition.
However, the examination requirement of the program plan, in accordance with Cleveland Electric Illuminating Corr.pany will comply with ASME 1977 Edition with Addenda through Summer 1978. Code cases listed in Reg. Guide 1.147 may be used when applicable.
The quality group classification system for radioactive water / steam-containing safety related components of water-cooled nuclear power plants is established by A
NRC Regulatory Guide 1.26, in conjunction with 30.55a of 10 CFR 50.
2.2 DEFINITION OF OWNER INTENT In accordance with the requirements set forth by 10CFR 50.55a, the Perry Nuclear Power Plant, Unit 1 PSI Program Plan must comply with the requirements of the ASME Code no earlier than those of the Winter 1972 Addenda of the 1971 edition.
However, in order to adopt a more recently accepted code with addenda, Cfa eland Electric Illuminating Company has elected to comply with the 1977 lidition of the Code up to and including the Summer 1978 Addenda.
80A4420 DOCUMENT NO.
m 6
30 PAGE OF NUCt. EAR ENERGY SERVICES, INC.
l b
Accordingly, this Program Plan provides the details necessary for performing the Preservice Inspection of the Perry Nuclear Power Plant Unit 1, Group A, B and C nuclear safety related piping system and components. The plan schedules all required condestructive examinations of piping systems within the Group A, B and C boundaries once, prior to initial startup, in accordance with ASME Section XI, Subsections IWA, IWB, IWC and IWD.
In addition, an augmented Inservice Inspection Program (provided later) will be implemented on high energy piping systems which penetrate containment for which the effects of postulated pipe breaks would be unacceptable.
This program will include branch lines which fall within augmented Inservice Inspection boundary up to the first pipe whip restraint beyond the branch line isolation valve.
- 3. PSI PROGRAM PLAN BOOK DESCRIPTION 3.1 DOCUMENT DESIGNATIONS Listed in Table 3.1 are the documents that constitute the plan and schedule of examinations for the PSI Program Plan. Any additional Class 3 systems and augmented inspection examinations will be identified later. Component support examinations to requirements of subsection IWF will be identified later by others.
l TABLE 3.1 Program Plan and System Documents i
Number Document Title l
i 30A4420 Preservice Inspection Program Plan for the Perry Nuclear P.ower Plant, Unit 1 80A4421 PSI Program Plan: Reactor Pressure Vessel l
80A4422 PSI Program Plan: Residual Heat Removal System FORM se NES 205 2/80
DOCUMENT NO.
80A4420 7
30 PAGE OF NUCLEAR ENERGY SERVICES. INC.
TABLE 3.1 cont.
Program Plan and System Documents Number Document Title 80A4423 PSI Program Plan: Low Pressure Core Spray System 80A4424 PSI Program Plan: High Pressure Core Spray System 80A4423 PSI Program Plan: Reactor Core Isolation Cooling System 80A4426 PSI Program Plan: Feedwater System 30A4427 PSI Program Plan: Main Steam System 30A4428 PSI Program Plan: Reactor Recirculation System 80A4429 PSI Program Plan: Reactor Water Clean Up System 80A4430 PSI Program Plan: Control Rod Drive Hydraulic System 30A4431 PSI Program Plan: Standby Liquid Control System Listed in Table 3.2 are the NES Controlled Documents supporting the development of this PSI Program Plan.
TABLE 3.2 General Reference Documents Number Document Title 80A9068 Training and Certification of Nondestructive Examination Personnel 30A9069 Certification of Visual Examination Personnel 81 A0268 Quality Assurance Program Plan for the Perry Nuclear Power Plant, Units 1 & 2 FORM = NES 205 2/80 1
DOCUMENT NO.
11 PAGE OF NUCLEAR ENERGY SERVICES, INC.
3.2 ZONE DESIGNATIONS The plant has been subdivided into smaller areas of interest called zones usually delineated by floors. This system of zone designations has been developed for the purpose of aiding the examiners in locating welds and components to be examined. Table 3.3 lists the figures defining these zones and the orientation of equipment within the zones.
TABLE 3.3 Zone Figures A-1 Zone Designations A-2 Floor Plan El 574'-10" A-3 Floor Plan El 599'-9" A4 Floor Plan El 620'-6" A-5 Floor Plan El 642'-0" A-6 Floor Plan El 664'-7" l
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Above Floor El. 574' 10" nev: 0 FIG. No.
A-2 et CH oaTE1/5/78 e CJat oAre f/dsr Perry Unit i 5532 O
FORM 8 NES 205 2/80
80A4420 DOCUMENT NO.
11
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80A4420 DOCUMENT NO.
,, 51 oAGE OF NUCLEAR ENERGY SERVICES. NC.
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A-5 et CH onre1/5/78 e en DATE 8[6[W lC "C
Perry Unit i 5532 FORM #NES 205 2/80
80A4420 DOCUMENT NO.
11 14 30 PAGE OF C'i NUCLEAR ENERGY SERVCES, INC.
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- A-6 en CH oart:l/5/78 e cn care 4 /sr Perry Unit 1 5532 FORM #NES 205 2/80
DOCUMENT NO.
80A4420 11 NUCt. EAR ENERGY SERVICES, INC.
3.3 EXCEPTIONS b
I The basis for exceptions to the requirements of Section XI are presented in the individual PSI Program Plan sections for each system.
Exceptions to Code required examinations may be authorized by the regulatory authority, as allowed by 10r CFR 50.55 a(a)(2), 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 provide an acceptable level of quality and safety.
3.4 EXEMPTIONS 1
The following exemptions from examination requirements are applicable to Quality Group A, B, and C piping systems:
3.4.1 Quality Group A All component connections, piping, and associated valves of 1" nominal size or smaller are exempt from examination, as allowed by ASME Section XI, Subparagraph IWB-1220(b).
In addition to the above exemption, all components less than 2.36" ID for water service and 3.0" ID for steam service are exempt from examination requirements.
This exemption, allowed by Subparagraph IWB-1220(a), is based on the exclusion diameter for normal makeup.
3.4.2 Quality Group B yh All component connections, piping, and associated valves and vessels of 4" nominal pipe size and smaller are exempt, as allowed by subparagraph IWC-1220(c). In addition to the above exemption, all components in systems other than the Residual Heat Removal and Emergency Core Cooling systems where both the design pressure and temperature are equal to or less than 275 PSIG and 2000F respectively are exempt from examination 1
l 1
FORM # NES 205 2/80
DOCUMENT NO.
80A4420 PAGE 16 op 30 NUCLEAR ENERGY SERVICES, INC.
requirements, as allowed by Subparagraph IWC-1220(b). Also, components that during normal plant operating conditions are not required to operate or function but remain flooded at 80% operating pressure may be exempted, as allowed by Subparagraph IWC-1220(a).
3.4.3 Quality Group A, Group B, and Group C
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For the purpose of system hydrostatic test, open-ended portions of suction or drain lines from a storage tank extending to the first datoff valve are considered as an extension of the storage tank.
Open-ended portions of nonclosed systems shall have tested or observed unimpaired flow during system operation in lieu of a system pressur'e test.
3.4.4 Exempt Components b
All Class ! Quality Group A components exempted from examination requirements by IWB-1220 shall be visually examined during system hydrostatic pressure tests per Category B-P requirements of Table IWB-2500.
All Class 2 Quality Group B pressure-retaining components exempted from examination requirements by IWC-1220 shall be examined during system hydrostatic pressure tests, in accordance with IWA-5000 and IWC-5000.
3.5 QUALITY ASSURANCE j
The NES Quality Assurance Program Plan (QAPP), Document 81 A0268, governs the design review and implementation of the Perry 5I Program Plan.
This document is in accordance with the requirements of the NES ISI Quality Assurance Manual (80A9021), which is in compliance with Appendix B of 10 CFR
- 50. The QAPP includes the detailed quality assurance requirements that are common to all activities of the program including organization, management,
- liaison, examination implementations, control of inspection
- records,
~
FORM # NES 205 2/80
DOCUMENT NO.
80A4420 PAGE I7 OF 30
. NUCLEAR ENERGY SERVICES, INC.
qualifications of personnel, materials and procedures, etc.
The QAPP is presented as part of the ISI Program Plan.
3.6 EXAMINATION PROCEDURES d
Subarticle IWA-1400 of Section XI requires the development and preparation of written examination procedures necessary for the cond'uct of the nondestructive examinations associated with PSI operations. The written procedures for the performance of visual, surface, and volumetric examinations are referenced in Table 3.4.
Visual Testing (VT) examination is employed to provide a report of the general condition of the part, component or surface to be examined; including such conditions as scratches, wear, cracks, corrosion or erosion on the surfaces; misalignment or movement of the part or component; or any evidence of leaking.
VT examinations are applicable to welds, support members, valves, pumps, fasteners, etc. The NES VT Examination Procedure is based on the requirements of Paragraph IWA-2210 of Section XI.
Liquid Penetrant Testing (PT) examination is specified as the surface examination method to delineate or verify the presence of cracks or discontinuities open to the examination surface.
The NES PT Examination Procedure is based on the requirements of Paragraph IWA-2222 of Section XL The Ultrasonic (pulse echo) Testing (UT) examination is selected as the volumetric examination method to indicate the presence of subsurface discontinuities by examining the required volume of metal contained beneath the surface to be examined. The NES UT Examination Procedures are based on Appendix III of Section XI and Articles 4 and 5 of Section V.
3.7 ULTRASONIC TESTING CALIBRATION STANDARDS A
The calibration standard design drawings are presented as part of the PSI FORM # NES 205 2/80
^
DOCUMENT NO.
PAGE OF NUCLEAR ENERGY SERVICES, INC.
Program Plan. Table 3.5 lists all UT Calibration Standards required to perform the UT examinations. All calibration standards are retained on site.
The UT examination calibration standard design and material selection is in accordance with Subarticle 111-3400 of Appendix III to Section XI. In addition to the required notches, drilled holes have been installed as additional reflectors in accordance with the provisions of Article 5 of Section V of the Code. These additional reflectors are allowed by Paragraph III-3400 of Appendix III of Section XI.
i FORM a NES 205 2/80
80A4420 DOCUMENT NO.
NUCLEAR ENERGY SERVICES, INC.
TABLE 3.4 Reference NDE Procedures 80 A0182 Ultrasonic Examination General Requirements 80 A0183 Liquid Penetrant Examination Procedures 80A0184 Visual Examination Procedure 80 A0185 Magnetic Particle Examination Procedure 80 A0186 Ultrasonic Examination Procedure For Ferritic Piping 80 A0187 Ultrasonic Examination Procedure For Austenitic Piping 80 A0189 Ultrasonic Examination Procedure For Reactor Vessel To Flange Weld and Flange Ligament Areas 80A0190 Ultrasonic Examination Procedure For Nozzle Inner Radil 80A0191 Ultrasonic Examination Procedure For Reactor Vessel Welds 80 A0192 Ultrasonic Examination Procedure For Closure Head Welds and Nozzle Welds 80A0193 Ultrasonic Examination Procedure For Closure Head Nozzle to Flang? Weld 80A0194 Ultrasonic Examination Procedure For Nozzle To Vessel Welds 80A0195 Ultrasonic Examination Procedure For Nozzle Safe End and Transition Welds 80A0196 Ultrasonic Examination Procedure For Component Bolts, Studs, and Nuts 80A0206 Ultrasonic Examination Procedure For Integrally Welded Pipe Supports and Attachments 80A0207 Ultrasonic Examination Procedure For Residual Heat Removal Heat Exchanger Welds 80A0208 Automated Ultrasonic Examination Procedure For Reactor Vessel Welds 80A0209 Automated Ultrasonic Examination Procedure For Reactor Vessel Nozzle Welds 80A0210 Automated Ultrasonic Examination Procedure For Nozzle Inner Radii 80A0211 Automated Ultrasonic Examination Procedure For Nozzle Safe End and Transition Welds i
l FORM 8 NES 205 2/80
80A4420 DOCUMENT NO.
11 PAGE OF NUCLEAR EFIRGY SERVICES. INC.
TABLE 3.5 Program Plan Calibration Standards Material Title Schedule Specification Drawing No.
PY-6-80-CS 0.432" SA 106, Grade B 80C0198 PY-6-120-CS 0.562" SA 106, Grade B 80C0198 PY-10-80-CS 0.593" SA 106, Grade B 80C0198 PY-10-100-CS 0.718" SA 106, Grade B 80C0198 PY-12-80-CS 0.687" SA 106, Grade B 80C0198 PY-12-100-CS 0.843" SA 106, Grade B 80C0198 PY-12-120-CS 1.00" SA 106, Grade B 80C0198 PY-14-80-CS 0.750" SA 106, Grade B 80C0198 PY-1840-CS 0.562" SA 106, Grade B 80C0198 PY-2040-CS 0.594" SA 106, Gra'de B 80C0198 PY-24-40-CS 0.687" SA 106, Grade B 80C0198 PY-16-100-CS 1.031" SA 106, Grade B 80C0199 PY-20-80-CS 1.031" SA 106, Grade B 80C0199 PY-20-100-CS 1.281" SA 106, Grade B 80C0199 PY-26-80-CS 1.499" SA 155, Grade KCF 70 80C0199 PY-26-XXI-CS 1.147" SA 155, Grade KCF 70 80C0199 PY-26-XX2-CS 1.321" SA 106, Grade B 80C0199 PYA 80-CS 0.337" SA 106, Grade B 80A7387
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PYA-X X I-CS-F 0.337" SA 234, WPB 30D7385 PYA-XXI-SS 0.325" SA 358, TP 304 80D7385 PY-6-XX I-CS-F 0.562" SA 234, WPB 80D7385 P Y-8-100-CS 0.594" SA 106, Grade B 80D7385 PY-8-XX 1-CS-F 0.594" SA 234, WPB 80D7385 PY-10-XX I-CS-F 0.718" SA 234, WPB 80D7385 PY-12-XX I-CS-F 0.688" SA 234, WPB 30D7385 PY-12-XX2-CS-F 0.843" SA 234, WPB 80D7385 PY-12-XXI-SS 0.700" SA 358, TP 304 80D7385 PY-12-80-SS-F 0.685" SA 403, WP 304 W 80D7385 PY-14-XXI-CS-F 0.750" SA 234, WPB 80D7385 l
P Y-18-XX 1-CS-F 0.562" SA 234, WPB 80D7385 PY-18-XXI-SS-F 0.562" SA 403, WP 304 80D7385 FORM # NES 205 2/80
80A4420 DOCUMENT NO.
21 PAGE op NUCLEAR ENERGY SERVICES, INC.
TABLE 3.5 (continued)
Program Plan Calibration Standards Nominal Material Title ThicL ness Specification Drawing No.
d PY-20-XX I-CS-F 0.594" SA 234, WPB 80 07385 PY-24-XX I-CS-F 0.687" SA 234, WPB 80D7385 PY-10-XX2-CS-F 1.45" SA 105 80 D7386 PY-12-XX3-CS-F 1.312" SA 234, WPB 80 D7386 P Y-16-XX I-CS-F 1.031" SA 234, WPB 80D7386 PY-16-100-SS 1.031" SA 358, TP 304 80 D7386 PY-20-120-CS 1.500" SA 106, Grade B 80D7386 PY-20-XXI-SS-F 1.281" SA 182, F 316 L 80D7386 PY-22-XX I-SS 1.006" SA 358, TP 304 80D7386 PY-22-XX1-SS-F 1.13" 5A 403, WP 304 80D7386 PY-24-XX1-SS 1.386" SA 358, TP 304 80D7386 PY-24-XXI-SS-F 1.735" SA 403, WP 304 80D7386 PY-24-XX2-SS-F 1.400" SA 403, WP 304 80D7386 PY-26-XX I-CS-F 1.414" SA 234, WPB 80D7386 PY-28-140-CS 2.406" SA 106, Grade C 80 D7386 PY-IR-RH R Later SA 105 Later S A 105-CS PY-STUD-LPCS 2.25"&
SA 193 GR B7 80D7550 d
2.25 - CS
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PY-STUD-RR-3"4 SA 540 GR B23, CLA 80D7549 3 - CS PY-STUD-MS-2.25"4 SA 540 BR B23, CL5 80D7551 2.25 - CS PY-1.5-RHR LATER LATER 80D7548 SAI6GR70-CS PY-Valve-XXI-CS 2.2" LATER 80D7547 PY-Valve-XX2-CS 1.5" LATER 80D7547 PY-Valve-XX3-CS 1.12" LATER 80D7547 I
FORM # NES 205 2/80
DOCUMENT NO.
80A4420 m
PAGE 22 OF 30 NUCl EAR ENERGY SERVICES. INC.
3.8 EVALUATION CRITERIA g
Evaluation of any indications detected during PSI shall be made in accordance with IWA-3000 of Section XI. Indications detected may be evaluated by other nondestructive methods, where practical, to assist in the determination (size, shape, location, orientation) before final disposition is made.
3.9 RECORDS AND REPORTS b
A system of records of the Preservice Inspection, plans, schedules and calibration standards; the examination results and reports, the corrective action required and taken, will be developed and maintained at the site in accordance with Article IWA-6000 of Section XI.
3.10 PERSONNEL QUALIFICATION REQUIREMENTS b
4 Personnel performing nondestructive examination operations shall be qualified with procedures prepared in accordance with SNT-TC-1A,1975 Edition, for the applicable examination technique and methods as required by Article IWA-2300 of Section XI. All examinations shall be performed and the results evaluated by qualified nondestructive examination personnel.
For those nondestructive examination methods not covered by SNT-TC-1 A documents, NES shall qualify personnel on the particular method involved. The NES procedures for such qualification provide uniform programs of training, evaluation, and certification of personnel are included in Table 3.2.
3.11 PRE-EXAMINATION REQUIREMENTS 4
General provisions for accessibility have been defined by Article IWA-1500 of Section XI of the ASME Code.
1.
All systems and components that require inspection in accordance with the requirements of ASME Section XI will be designed with adequate physical access to allow the required inspection.
FORM 8 NES 205 2/80
0A%20 DOCUMENT NO.
11 NUCt. EAR ENERGY SERVICES, INC.
2.
Piping systems requiring ultrasonic inspection will be designed so that all welds requiring inspection are physically accessible for inspection with ultrasonic equipment.
A.
Access will be provided by _ leaving adequate space around pipes at these welds and by means of removable insulation and shielding as required.
B.
Pipes welded to fittings will be designed to permit meaningful examination by avoidance of irregular surface geometries.
C.
The surface of welds will be smoothed and contoured to permit effective use of ultrasonic. transducers or surface examination indicators.
D.
Piping systems requiring surface or visual examination will be designed to allow access and visibility adequate for performance of such examinations.
3.12 PIPING SYSTEM DOCUMENTS
$\\
Each piping system document contains the following groups of information that are to be used for the preservice inspection of the Perry Nuclear Power Plant Unit 1.
1.
Exemptions and Exceptions These are lists of the basis for exemptions and exceptions to the requirements of Section XI, as claimed in the Preservice Inspection Plan for those areas that are exempted by the code or cannot be. examined either fully or in part because of limitations in accessibility, material, or design.
FORM # NES 205 2/80
80AM20 DOCUMENT NO.
NUCLEAR ENERGY SERVCES, INC.
2.
System Classification d
The Perry Nuclear Power Plant Unit 1 System ASME Group A, B, and C, boundaries have been established in accordance with Reg. Guide 1.26.
3.
Program Plan and Schedule The specific examination requirements for the Perry Unit 1 System Preservice Inspection Plan are defined in the Program Plan and Schedule.
Each weld or other examination area is designated by a unique identification number along with the applicable procedure number, examination category and method, and calibration standard number, if required for ultrasonic examinations. Each weld has been given a unique designation number in the Program Plan and Schedule. Table 3.6 provides a key to the designator notation. Exam items are divided by system and further subdivided according to the weld or hanger figure that they appear Multiple examination requirements of the same component are listed
~
on.
in the Schedule appearing together. Hanger and component examinations follow the piping weld examinations within each sytem.
4.
System Isometrics and Sketches The piping isometric drawings show the piping for plant systems, delineating the identification of components subject to examination.
FORM # NES 205 2/80 j
DOCUMENT NO.
80A4420 11 NUCLEAR ENERGY SERVICES, INC.
TABLE 3.6 DESIGNATIONS A.
Piping Systems have been designated as follows:
b System Designation Reactor Pressure Vessel RPV Residual Heat Removal RHR Low Pressure LPCS Core Spray High Pressure HPCS Core Spray Reactor Core Isolation Cooling RCIC Feedwater FW Main Steam MS Reactor Recirculation RR Reactor Water Clean Up RWCU Control Rod Drive CRD Standby Liquid Control SLC B.
Pipe Weld Identification according to the following format:
n-XXX-AAAA Where n
is
" Unit Number" XXX is
" System Prefix" Per Piping System abbreviation A A A A is Weld Identification Number C.
Component Examination will have the following similar format:
n-XXX-AAAAA-ZZZ Where n
is
" Unit Number" XXX is
" System Prefix" Per Piping System abbreviation AAAAA is Component Identification Number ZZZ is Component Weld Identification Number FORM 8 NES 205 2/80
80A %20 DOCUMENT NO.
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NUCLEAR ENERGY SERVICES, INC.
D.
A suffix may designate particular exam areas or additional (repair) field welds.
k Suffix Key:
A New or additional weld (successive letters are required for field identification)
B Bolting (Studs, Nuts, Washers, etc. as applicable to component identification only)
Di Longitudinal Seam, (Downstream) g D2 Longitudinal Seam (Downstream)
U1 Longitudinal Seam (Upstream)
U2 Longitudinal Seam (Upstream)
N Nuts R
Repair Weld Stud Studs i
IR Inner Radius NZ Nozzle i
Note:
HYD denotes Visual Examination During Hydrostatic Test N/A denotes NOT APPLICABLE N/S denotes NOT SPECIFIED FORM sNES 205 2/80
DOCUMENT NO.
80A4420 11 NUCLEAR ENERGY SERVICES. INC.
E.
PERRY EXAMINATION CODE b
MT Magnetic Particle Examination PT Liquid Penetrant Examination RT Radiographic Examination UT Ultrasonic Examination VT-1 Visual Examination VT-2 Hydro-Visual Examination VT-3 Visual Examination VT-4 Visual Examination 3.13 VALVE AND PUMP GROUPING b
1 To satisfy the requirements of category B-M-2 (valve bodies greater than 4" nominal size), B-L-2 pump casing, and C-G (pump & valve casing / body welds) the internal pressure boundary surfaces shall be visually examined for one valve / pump within each group of valve / pump listed in Table 3.7, per the preservice examination requirements of IWB-2100.
Valves / pumps are grouped according to same body constructional design, manufacturing method, manufacturer and performance of similar function in a system.
TABLE 3.7 g
PUMP - GROUPING (B-L-2)
Group //
Manufacturer System Pump //
Description l
1 Byron Jackson Reactor B33-C001 A Centrifugal l
Recirculation B33-C001B l
l Valve Grouping (B-M-2)
Group //
Manufacturer System Valve //
Description I
Borg-Warner Residual Heat E12-F008 20" Gate Valve Removal E12-F009 E12-F010 II Borg-Warner Residual Heat E12-F039 A,B,C 12" Gate Valve Removal E12-F042 A,B,C FORM 2 NES 205 2/80
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TABLE 3.7 (Cont'd) d Valve Grouping (B-M-2)
Group #
Manufacturer System Valve #
Description III Rockwell Residual Heat E12-F041 A,B,C 12" Gate Valve International Removal IV Borg-Warner Residual Heat E12-F019 6" Check Valve Removal V
Borg-Warner Residual Heat E12-F023 6" Globe Valve Removal I
Borg-Warner Low Pressure E21-F007 12" Gate Valve Core Spray 11 Borg-Warner Low Pressure E21-F006 12" Gate Valve Core Spray E21-F005 i
Borg-Warner High Pressure E22-F036 12' Gate Valve Core Spray II Borg-Warner High Pressure E22-F005 12" Gate Valve Core Spray III Borg-Warner High Pressure E22-F004 12" Centrol Valve Core Spray I
Borg-Warner Reactor Core E51-F065 6" Disc Valve Isolation Cooling 11 Rockwell Reactor Core E51-F066 6" CheckValve International Isolation Cooling 111 Borg-Warner Reactor Core E51-F013 6" Gate Valve Isolation Cooling IV Borg-Warner Reactor Core E51-F063 10" Gate Valve Isolation Cooling E51-F064 FORM 8 NES 205 2/80 m'mm wr,m m'm m-
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I d
DOCUMENT NO.
80A4420 NUCLEAR ENERGY SERVICES, INC.
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/
i TABLE 3.7 (Cont'd) b
~
Valve Grouping (B-M-2)
Group #
Manufacturer System Valve #
Description I
Dikkers Main Steam B-21-F047 B,C,D 8" v 10" Safety B21-F047 F,G,H Relief Valve B21-F041 A,B,C B21-F041 D,E,F,G,K B21-F051 A,B,C B21-F051 D,G II ktwood & Morril Main Steam B21-F028 A,B,C,D 26" Globe Valve B21-F022 A,B,C,D I
Roc'hvell Feedwater B21-F032 A,B 20" Check Valve International B21-F559 A,B II Borg-Warner Feedwater B21-F560 A,B 20" Gate Valve
/
r I
/ Anchor / Darling Reactor B33-F067 A,B 24" Gate Valve Recirculation II Anchor / Darling Reactor B33-F023 A,B 22" Gate Valve Recirculation
/,
Ill
, Fisher Control,
Reactor B33-F060 A,B 24" Ball Valve Recirculation I
Borg-Warner
~ R'eactor Water G33-F004 6" Gate Valve Clean-up G33-F001 Valve Grouping (C-G) g Group #
Manufacturer Systen$
Valve #
Description r
i
.Rockwell Residual Heat E12-F055 A,B 6" Safety International Removal Relief Valve j
I Borg-Warner High Pressure E22-F003 6" Check Valve
)
Core Spray I!
Borg-Warner Algh Pressure E22-F026 6" Gate Valve Core Spray b
FOAM # NES 205 2/80
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I Valve Grouping (C-G) g Group //
Manufacturer System Valve #
Description I
Bcrg-Warner Reactor Core E51-F502 6" Gate Valve Isolation Cooling i
l l
l l
I FOAM 8 NES 205 2/80
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