ML19347F440

Preservice Insp Program Plan,General Ref Text

ML19347F440
Person / Time
Site:	Perry
Issue date:	04/14/1981
From:	NUCLEAR ENERGY SERVICES, INC.
To:
Shared Package
ML19347F438	List: ML19347F437 ML19347F440
References
80A4420, NUDOCS 8105190276
Download: ML19347F440 (19)

Text

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NUCLEAR ENERGY SERVICES, INC. 10 PAGE 1 nF o .

P00R ORIGINAI. i PSI PROGRAM PLAN:

GENERAL REFERENCE TEXT PERRY NUCLEAR POWER PLANT, UNIT 1 Prepared For CLEVELAND ELECTRIC ILLUMINATING COMPANY l _

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l DOCUMENT NO. 80A4420 l NUCLEAR ENERGY SERVICES. INC.

1 O 1 TABLE OF CONTENTS l

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1. INTRODUCTION 4

2. BASES FOR PRESERVICE IN513 ECTION PROGRAM 5

3. PRESERVICE INSPECTION PROGRAM PLAN DESCRIPTION 6 3.1 Document Designations 6 3.2 Zone Designations 7 3.3 Exemptions and Exceptions 14 3.3.1 Quality Group A 14 3.3.2 Quality Group B 14 3.3.3 Quality Group C 15 3.3.4 Exempt Components 15 3.4 Quality Assurance 15 3.5 Examination Procedures 15 3.6 Ultrasonic Testing Calibration Standards 16

- 3.7 Evaluation Criteria 18 Y

3.3 Records and Reports - 13 3.9 Personnel Qualification Requirements IS 3.10 Pre-examination Requirements 18 LIST OF TABLES 3.1 Program Plan and System Documents 6 3.2 General Reference Documents 7 3.3 Zone Figures 7 3.4 Program Plan Calibration Standards 17

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DOCUMENT NO. 80A4420 PAGE 4 OF 10 NUCLEAR ENERGY SERVICES. INC.

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1. INTRODUCTION This Program Plan has been prepared to fulfill the Preservice Inspection (PSI) requirements for the nuclear system components of Perry Nuclear Power Plant, Unit 1, owned by the Cleveland Electric Illuminating Company. This 9rogram 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).

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 (EPV) Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1977 Edition with Adcenda through Summer 1973. The extent of examination is determined by requirements of Addenda through Summer 1975 of Category B-3 for Class 1 pipe welds; of Categories C-F and C-G for Class 2 pipe welds of the Residual Heat Removal System, Emergency Core Cooling System, and Containment Heat Removal System; and of Categories C-F and C-G for other Class 2 System pipe welds.

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-specific examinations. The examinations shall comply with Section XI requirements of examination categories, methods, techniques, and procedures; of personnel qualificatic,ns; of documentation, mapping, and evaluation of inspection results; and of disposition and repair.

g 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.

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my DOCUMENT NO. 80A4420 PAGE 9 OF 19 NUC1. EAR ENERGY SERVICES. INC.

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2. BASES FOR PRESERVICE INSPECTION PROGRAM i The ISI and PSI requirements stipulated by 10 CFR 50.55 a(g)(3) establish the edition of Section XI of the ASME 'V Code applicable to the examination areas. Addenda subsequent to the Winter 1977 Addenda are considered in effect after the date of publication of the addenda, and af ter they are incorporated by reference in paragraph (b) of 10 CFR 50.55 a.

The construction permit for Perry Unit I was issued May 3,1977. Thus,in accordance with 10 CFR 50.55 a (g)(3), Class 1, 2, and 3 components shall meet the PSI requirements set forth in Section XI of those editions or Addenda of the Code that were applied to the construction of the component. However, it is the intent of Cleveland Electric 111uminating Company to comply with the PSI requirements of the 1977 Editicnof the Code with Addenda through Summer 1973, as provided 'by q subparagraph (v) of 10 CFR 50.55 a (g)(3). .

V NRC Regulatory Guide 1.26, " Quality Group Classifications and Standards," in conjunction with 10 CFR 50.55a, establishes the Quality Group classifications and standards for radioactive water and steam-containing components important to the safety of water-cooled nuclear power plants. Guide 1.26 defines the Quality Group Classification System consisting of four Quality Groups, A through D. The initial group of this system, per Regulatory Guide 1.26,is described in 10 CFR 50.55 a, which references the definition of Reactor Coolant Pressure Boundary given in subsection 10 l CFR 50.2. The remaining groups are defined by Regulatory Guide 1.26, as are the applicable safety standards.

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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 will be identified later.

TABLE 3.1 Program Plan and System Documents Number Document Title 80A4420 Preservice Inspection Program Plan for the Perry Nuclear

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Plant, Unit 1 80A4421 PSI Program Plan: Reactor Pressure Vessel 80A4422 PSI Prograrn Plan: Residual Heat Removal System 30A4423 PSI Program Plan: Low Pressure Core Spray System 80A4424 PSI Program Plan: High Pressure Core Spray System 80A4425 PSI Program Plan: Reactor Core Isolation Cocling System 80A4426 PSI Program Plan: Feedwater System l

80A4427 PSI Program Plan: Main Steam System 80A4428 PSI Program Plan: Reactor Recirculation System 80A4429 PSI Program Plan: Reactor Water Clean Up Sys*em 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 L x uments supporting the development of this PSI Program Plan and not identified in the Master Document List,30A0181, which is also incorporated by this reference.

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l TABLE 3 2 General Reference Documents Number Document Title 30A9068 Training and Certification of Nondestructive Examination Personnel 30A9069 Certification of Visual Examination Personnel SIA0263 Quality Assurance Program Plan for the Perry Nuclear Power Plant, Units 1 & 2 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 airling the examiners in locating welds anc: components to be examined. Table 2.3 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" A-4 Floor Plan El 620'-6" A-5 Floor Plan El 642'-0" A-6 Floor Plan E:. 664'-7"

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PAGE T4 OF 10 NUCt. EAR ENERGY SERVICES. INC.

3.3 EXEMPTIONS AND EXCEPTIONS The basis for exemptions and exceptions to the requirements of Section XIin the PSI Program Plan are presented. Exceptions to Code required examinations may be authorized by the regulatory authority, as allowed by 10 CFR 50.55 a(a)(2),

provided that design fabrication, installation, testing and inspection performed in compliance with Codes and Section XI requirements , ould result in t.ardship without a compensating increase in the level of quality and safety, or provided that the croposed alternative examination will provide an acceptable level of quality and afety.

The following exemptions from examination requirements are applicable to Quality Group A, B, and C piping systems:

3.3.1 Quality Grouc A All component connections, pioing, and associated va. ves of 1" nominal size or smaller are exempt from examination, as allowed y ASME Section XI,

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Subparagraph IWB-1220(M. In addition to the at. ie exemption, all components less than 2.36" ID for water service and 4.72" ID for steam service are exempt frwr. examination requirements. This exemption, allowed by Subparagraph IWB-1220(a), is based on the exclusion diameter for normal makeup.

3.3.2 Quality Grouo B 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 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 30% operating pressure may be

(- exempted, as allowed by Subparagraph IWC-1220(a).

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DOCUMENT NO. 80A4420 1

GE I9 OF 10 NUCLEAR ENERGY SERVICES. INC.

( 3.3.3 Quality Grouo C For the purpose of system hydrostatic test, open-ended portions of suction or drain lines from a storage tank extending to the first shutoff vaive 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 pressure test.

3.3.4 Exemot Comoonents All Class 1 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 di ring system hydrostatic pressure tests, in accordance with IWA-5000 and IWC-5000.

3.4 QUALITY ASSURANCE The NES Quality Assurance Program Plan (QAPP), Document SIA0268, governs the design review and implementation of the Perry ISI Program Plan. This document is in accordance with the requirements of the NES ISI Quality Assurance Manual (30A9021), 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, qualifications of personnel, materials and procedures, etc. The QAPP is presented as part of the ISI Program Plan.

3.5 EXAMINATION PRCCEDURES Subarticle IWA-1400 of Section XI requires the development and preparation of

\ written examination procedures necessary for the conduct of the nondestructive examinations associated with PSI operations. The written procedures for the FCCM c NES 2C5 2/80 ,

DOCUMENT NO. 80A4420

' PAGE 16 OF 10 NUCLEAR ENERGY SERVICES. INC.

p/ performance of visual, surface, and volumetric examination- are referenced in NES Master Document List,30A0lSI.

Visual Testing (VT) examination is employed to provide a report of the general condition cf 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 compone t; 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 Parag-aph I'VA-2210 of Section XI.

Liquid Penetrant Testing (PT) examination is specified as the surface examination method to de'ineate 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 XI.

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.

3.6 ULTRASONIC TESTING CALIBRATION STANDARDS The calibration standard design drawings are presented as part of the PSI Program Plan. Table 3.4 lists all UT Calibration Standards required to perform l the UT examinations. All calibration standards are retained on site.

The UT examination calibration standard design and material selection is in accordance with Subarticle III-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.

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V TABLE 3.4

\ Progren Plan Calibration Standards Material Title Line Class Schedule Soecification Drawing No.

PY-03-160-03 3" 0.433 SA 106, Grade B (Later)

PY-04-080-CS 4" 0.337 SA 106, Grade B PY-04-XXI-SS 4" D2-1 0.217 SA 353, Type 304, Class 1 PY-06-030-CS 6"D 1-1 SCH80 SA 106, Grade B PY-06-120-CS 6"DI-2 SCH 120 SA 106, Grade B PY-10-030-CS 10"DI-2 SCH 20 SA 106, Grade B PY-10-100-CS 10"D I-2 SCH 120 SA 106, Grade B PY-12-030-CS 12"D 1-1 SCH SO SA 106, Gcade B PY-12-100-CS 12"D I-2 SCH 100 SA 106, Grade B PY-12-120-CS 12"D I-2 SCH 120 SA 106, Grade B PY-12-XXI-SS 12"D2-1 0.575 Min. Wall SA 353, Type 304, Class 1 PY-16-100-CS 16" SCH 100 SA 106, Grade B PY-16-XXI-SS 16"D2-1 0.371 Min. Wall SA 358, Type 304, Class 1 PY-13-040-CS 13"G I-2 SCH 40 SA 106, Grade B

{ PY-13-405-SS 13"L2-2 SCH 405 SA 312, Type 3Q4, or SA 353, Type 304 PY-20-040-CS 20"GI-2 SCH 40 SA 106, Grade B PY-20-080-CS 20"D1-1 SCH30 SA 106, Grade B or SA 333, Grade 6 PY-20-100-CS 20" SCH 100 SA 106, Grade B PY-22-XXI-SS 22"D2-1 0.398 Min. Wall SA 35S, Type 304, Class 1 PY-22-XX2-SS 22"D2-1 1.073 Min. Wall SA 358, Type 304, Class 1 PY-24-040-CS 24"G I-2 SCH40 SA 106, Grade B PY-24-XX1-55 24"D2 1 1.212 6: 1.296 SA 353, Type 304, Class 1 Min. Wall PY-24-XX2-SS 24"D2-1 1.455 Min. Wall SA 358, Type 30'+ Class 1 PY-26-100-CS 26" SCH 100 SA 106, Grade B Key to Table Given: PY-NN-SSS-MM PY = The Perry Nuclear Power Plant NN = The Nominal Pipe Size N SSS = The Schedule or XXI, XX2 designating special wall pipe MM = Either carbon steel (CS) or stainless Steel, Type 304 (55).

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my DOCUMENT NO. 530A4420 E M OF M NUCLEAR ENERGY SERVICES. INC.

EVALUATION CRITERIA

'( 3.7 Evaluation of any indications detected during PSI shall be made in accordance )

with IWA-3000 of Section XI. Indications detected may be evaluate' d by other nondestructive methods, where practical, to assist in the determination (size,  !

shape, location, orientation) before final disposition is made.

3.3 RECORDS AND REPORTS 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 sito in accordance with Article IWA-6000 of Section XI.

3.9 PERSONNEL QUALIFICATION REQUIREMENTS 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 examina+ ions shall be performed and the results evaluated by qualified nondestructive examination personnel.

For those nondestructive examination methods not covered by SNT-TC-1A dccuments, NES shall qualify personnel on the particular method involved. The NES proceduas for such qualification provide uniform programs of training, evaluation, anr certification of personnel are included in Table 3.1.

3.10 PRE-EXAMINATION REQUIREMENTS 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.

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DOCUMENT NO. 80A4420 G OF M NUCLEAR ENERGY SERVICES. INC.

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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 fitt;ngs 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 ultrasen.c 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 examic.ation.

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