ML20196A841

From kanterella
Jump to navigation Jump to search
Rev 4 to 80A8608, Inservice Insp Program Plan,General Text for Shoreham Nuclear Power Plant Unit 1
ML20196A841
Person / Time
Site: Shoreham File:Long Island Lighting Company icon.png
Issue date: 01/25/1988
From:
NUCLEAR ENERGY SERVICES, INC.
To:
Shared Package
ML20196A839 List:
References
80A8608, NUDOCS 8802050182
Download: ML20196A841 (23)
v • d • e


Text

'

I A.F NUCLEAR ENERGY SERVCES DOCUMENT NO, 80A8608 R EV. 4 PAGE I OF 24 (jD

\

INSERVICE INSPECTION PROGRAM PLAN GENERAL TEXT FOR LONG ISLAND LIGHTING COMPANY

' )' r~ ~;3 ,':)

C Q

SHOREHAM NUCLEAR POWER PLANT UNIT 1 A

JJeCl ADDisc3 tion CODy No Assigned To Shoreham Project #5536 APPROVALS TITL E / DEPT. SIGN ATURE D ATE REV NO PREPARED BY Project De pt.

Manager Manage r QA Manager 0

N 2

N ffAM.bl.D YN):sWx # 4 9 l 8' ; r %:#IG"^ __

j s  ;

' 1 e

P.0 o 4.T. R.

. l l.F D_ P i.3Y.

I tra *

  • 1 V *T O OTAU ) 0 ((1 l 8 IN 1 ' "I I # 83M' # N l

9 i

10 11 8802050102 DR 080129 '

ADOCK 05000322 ro w

, e g gg REVISION 1.0G NUCLEAR ENERGY SERVICES. INC.

PAGE

  • ^*'*

OF p "f[

, DATE DESCRIPTION APPROVAL 1 7/10/84 -

See CRA 4460 Revision includes 6,/)

editorial changes and the addition of new information 2 11/5/84 2 Corrected typo's.

6/J h See CRA 4792 3 f5/8/85 2,4 6,9,10,13,22,23,24 See CRA 0 5302. (('g*(1 ,b [ ') ( , ( )

1/25/88 lb 1 4

6, See CRA 6754 incorporated custo:ner co:ments

[ [} [

i l

l i l l l 1  :  :

i i

o i  !

i L q  ;

i

! l t

l i i

l l l l l

\ \ \

I i  ! I i  !

t i i t l

l F O R M e % E S 206 ;

my DOCUMENT NO. enA9ene 11 W NUCLEAR ENERGY SERVICES O'

TABLE OF CONTENTS PAGE

1. INTRODUCTION 4
2. BASES FOR INSERVICE INSPECTION PROGRAM 6 2.1 NRC Regulations 6 2.2 Definition of LILCO Intent 6 2.3 Methods of Examination 6 2.4 Schedule 7 2.5 Selection Criteria 11 2.5.1 Quality Group A 11 2.5.2 Quality Group B 2.5.3 Quality Group C 12 g

2.6 Augmented requirements 12 2.6.1 NUREG - OS00 (Break exclusion piping) 13  :

2.6.2 NUREC - 0619 13 j 2.6.3 NUREG - 0803 13 '

2.6.4 NUREG - 0313 13 2.6.5 IE Bulletin 30-13 14 l 2.6.6 IE Bulletin 30-07 14 2.7 Evaluntion Criteria 14 I I 2.3 Records and Reports 14 2.9 Personnel Qualification Requirements 15 2.10 Quality Assurance 16

3. INSERVICE INSPECTION PROGRAM SYSTEM 17 DOCUMENT DESCRIPTION 3.1 System Classifications 17 3.2 Exemptions 17 3.2.1 Quality Group A 19 3.2.2 Quality Group B 19 3.2.3 Quality Group C 19 3.3 Exceptions 20 3.4 Calibration Standards 20 3.5 Program Plan and Schedule 24 3.6 Isometric Figures and Sketches 24 TABLES 2-1 NDE Procedures 8 2-2 Inspection Program B Schedule 10 3-1 System Document List 13 3-2 Calibration Standards 21 I I FORM a NES 205 2/80

I DOCUMENT NO. 80A0608 m

11 NUCLEAR ENERGY SERVK ES MGE 4 OF 2'4 l

\

1. INTRODUCTION The 10-year ISI Program Plan has been prepared to fulfill the Inservice Inspection requirements for the Shoreham Nuclear Power Plant, Unit 1.

In accordance with 10 CFR 50.55a, this unit is required to comply with the ASME Code Edition and Addenda in effect 12 months prior to the date of issuance of the operating license. The Code Edition and Addenda in effect is the Edition and Addenda referenced in 10CFR50.55a (b). It is the intent of the Inservice Inspection Program Plan to meet the requirements of the 1980 Edition of the ASME Code Section XI with Addenda through Winter 1981, subject to the following modifications as required or permitted by 10CFR$0.55a:

A. The extent and frequency of examination for Quality Group A (Class 1) Piping (Table IWB-2500-1, Category B-3) will be in accordance with Table IWB-2500 and Table IWB-2600 Category B-] of Section XI,1974 Edition, Summer 1975 q g Addenda.

B. The examination of Quality Group B (Class 2) Piping will be in accordance d with the requirements of ASME Boiler and Pressure Vessel Code Case N-408. l The preservice requirements of the code do not apply to this 151 program.

l It is LILCO's intention to update the Inservice Inspection Program Plan every 10 years to comply with the edition of the ASME Code and Addenda in effect 12 months prior to the start of each 10 year interval, to the extent practical within the limitations of design, geometry and materials of construction of the components.

In addition to the ASME Section XI required examinations, the ISI program has been .

1 expanded to include augmented inservice examinations which comply with the j following documents: l l

l l I FOAM a NES 205 2/80 l

my DOCUMENT NO. 964 une MGE < OF- u NUCLEAR ENERGY SERVCES O

V A. NUREG - 0S00 (Standard Review Plan) (Break Exclusion Piping) Section 3.6.1 "Plant Design for Protection Against Postulated Piping Failures in Fluid Systems Outside Containment."

8. NUREG - 0619 "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking".

C. NUREG - 0803 "Generic Safety Evaluation Report Regarding Integrity of BWR Scram System Piping".

D. NUREG - 0313 "Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping".

E. IE Bulletin No. 30-13 "Cracking in Core Spray Spargers".

}

F. lE Bulletin No. 30-07 "BWR Jet Pump Assembly Failure".

{

The Reactor Pressure Vessel examinations will be in compliance with Nuclear Regulatory Commission (NRC) Regulatory Guide 1.150,"Ultrasonic Testing of Reactor Vessel Welds during Preservice and Inservice Examinations".

l l FORM e NES 205 2/80

DOCUMENT NO. Rn A uns 11 NUCLEAR ENERGY SERVICES

'"GE O'  %

l l

(~N, s .

2. BASES FOR INSERVICE INSPECTION PROGRAM 2.1 NRC REGULATIONS l

The Code of Federal Regulations states, in 10 CFR 50.55a (g)(4), that the initial '

inservice examinations conducted during the first 10 years shall comply with the requirements of the Code edition and addenda approved for use by the NRC no more than 12 months prior to the date of issuance of the operating license. In addition, the inservice examinations conducted during each successive 10-year interval throughout the service life of the f acility shall comply to the requirements of the Code edition and addenda approved for use by the NRC no more than 12 months prior to the start of each 10-year interval.

The quality group classification system for radioactive water- and steam-containing components important to the safety of water-cooled nuclear power plants is established by NRC Regulatory Guide 1.26 in conjunction with Part

{ } $0.55a of 10 CFR 50. Regulatory Guide 1.26, "Quality Group Classification and Standards" defines the Quality Group Classification System as consisting of four Quality Groups, A through D. The oefinition of Quality Group A (Class 1) is provided by 10 CFR 50.2 (v) under "Reactor coolant pressure boundary". The definitions of Groups B, C and D are provided by Regulatory Guide 1.26.

)

2.2 DEFINITION OF LILCO INTENT The 1980 Edition of the ASME Code Section XI with Addenda through Winter 1981 is the latest code approved for use by the NRC and it is LILCO's intent to comply with the requirements of the Winter 1981 Addenda, subject to modifications as required or permitted by 10CFR50.55a.

2.3 METHODS OF EXAMINATION l

Methods for the inservice inspections are titled visual, surf ace and volumetric. l Each term describes a general method which permits a selection of different 4 g techniques restricted to that method to accommodate varying degrees of accessibility and radiation levels, and the automation of equipment to perform the examinations.

FORM s NES 205 2/80 l

m DOCUMENT NO. enaeene 11 NUCLEAR ENERGY SERVICES MGE r op n n

{ i s

' }

The visual examination is subdivided into four different types, VT-1, VT-2, VT-3 and VT-4. The VT-1 examination is conducted to determine the condition of the part, component or surf ace examined, including such conditions as cracks, wear, corrosion, erosion or physical damage. The VT-2 examination is conducted to locate evidence of leakage from pressure retaining components or abnormal leakage from components during the conduct of a system pressure, functional or hydrostatic test. The VT-3 examination is conducted to determine the general mechanical and structural conditions of components and their supports. The VT-4 examination is conducted to determine conditions relating to the operability of components or devices such as mechanical and hydraulic snubbers, supports and spring hangers.

A liquid penetrant examination is specified as the surface examination technique to delineate or verify the presence of cracks or discontinuities open to the examination surface. NES' liquid penetrant examination procedure is based on the requirements of Paragraph IWA-2222 of Section XI of the ASME Code.

( } Magnetic particle examination may be substituted for the liquid penetrant examination as an alternative surf ace examination technique.

The ultrasonic pulse echo examination is selected as the volumetric examination technique to indicate the presence of subsurface discontinuities by examining the volume of metal contained beneath the surface to be examined. NES' ultrasonic examination is based on the requirements of Paragraph IWA-2232 of Section XI of the ASME Code.

Table 2-1 includes those NDE procedures applicable to the ISI Program Plan.

2.4 SCHEDULE Examinations listed in the Inservice Inspection Program Plan shall be performed in accordance with the inspection program B as outlined in Section XI and Table l 2-2 unless otherwise noted. The Program Plan and Schedule Tables, which lists all the required examinations for the first interval (10 years), is divided into 3 g g periods (40 months). In this way, approximately one third of the examinations will be completed every period (40 months). l FOAM e NES 205 2/80 '

m DOCUMENT NO. en A 9 tsn e NUCLEAR ENERGY SERVK:ES PAGE  ? OF S i; O

TABLE 2-1 NDE PROCEDURES Document No. Title 30A3131 Ultrasonic Examination Procedure for Ferritic Piping & Long Welds.  ;

SOA3132 Liquid Penetrant Examination Procedure.

80A3133 Visual Examination Procedure.

SOA3134 General Magnetic Particle Examination.

i 30A3135 Manual Ultrasonic Examination Procedure for Vessel Welds &

Support Skirt Weld.

1 SOA3136 Ultrasonic Examination Procedure for Closure Head Welds.  !

SOA3137 Ultrasonic Examination Procedure For Closure Head Nozzle Welds.

SOA3133 Manual Ultrasonic Examination Procedure for Closure Head Nozzle to Flange Welds.

g SOA3139 Ultrasonic Examination Procedure for Closure Head & Recirculation Pump & Valve Studs & Nuts.

SOA3140 Ultrasonic Examination Procedure for Vessel Flange Weld &

Ligaments.

S OA 3141 Manual Ultrasonic Examination Procedure for Nozzle to Vessel Welds.

SOA3142 Manual Ultrasonic Examination Procedure for Nozzle Inner Radias Areas.

SOA3143 Manual Ultrasonic Examination Procedure for Nozzle Safe-End &

Transition Welds.

SOA 3144 Automatic Ultrasonic Examination Procedure for Reactor Pressure l Vessel Welds.

30A3145 Automatic Ultrasonic Examination Procedure for Reactor Vessel Nozzle welds.

30A3146 Automatic Ultrasonic Examination Procedure for Nozzle Inner Radii.

30A3147 Remote Ultrasonic Examination Procedure for Nozzle Safe-End &

Transition Welds, g 30A3143 Ultrasonic Examination Procedure for Control Rod Drive Housing Welds.

FORM e NES 20S tiSo

DOCUMENT NO. RO A R(;oR I my PAGE 9 0F 24 NUCLEAR ENEROY SERVCES O TABLE 2-1 NDE PROCEDURES (Continued)

I Document No. Title 30A3149 Ultrasonic Examination Procedure for Residual tieat Removal Heat Exchanger Welds.

30A3150 Ultrasonic Examination Procedure for Austenitic Piping & jgh Longitudinal Welcs.

30A 3151 Ultrasonic Examination Procedure for Pipe Supports & Attachments.

30A3152 Ultrasonic Examination General Requirements.

SOA906S Procedure for Training and Certification of Nondestructive Examination Personnel.

SOA9069 Nuclear Inservice inspection Procedure for the Certification of Visual Examination Personnel.  !

q 30A9021 Inservice Inspection Program Quality Assurance Manual. I 80A0443 Quality Assurance Program Plan for Inservice Inspection Program, Shoreham.

1 s

l l FORM s NES 205 2/60

my DOCUMENT NO. R O A S f308 NUCt. EAR ENERGY SERVICES PAGE f n or 24 O

V TABLE 2-2 Inspection Program B Schedule inspection Calendar Years of  % Examinations Credited Interval Inspection Period

  • Plant Service ..tinim um Maximum 1 .

I 3 16 34 2 7 50 67 3 10 100 100 2 1 13 16 34 2 17 50 67 3 20 100 100 l l 3 1 23 16 34 2 27 50 67 3 30 100 100 4 1 33 16 34 l 2 37 30 100 3 40 100 100 l

Modifications to this schedule may occur as allowed by IWA-2400(c) of Section XI.

FORM e NES 205 2/B0

DOCUMENT No. 30A8603 M

PAGE 11 OF 24 NUCl. EAR ENERGY SERVICES O

U 2.5 SELECTION CRITERIA 2.5.1 Quality Group A Quality Group A components were selected for inspection in accordance with the requirements of subarticle IWB-1200 of the ASME Code Section XI 1980 Edition with Addenda through Winter 1981 with the exception of pipe welds. The extent and frequency of examinations of pipe welds were determined by the requirements of Table IWB-2500 and Table IWB-2600 Category B-J of Section XI 1974 Edition with Addenda through Summer 1975 as allowed by 10 CFR 50.55a (b)(2).

2.5.2 Quality Group B Quality Group B components were selected for inspection in accordance b with the requirements of subarticle IWC-1200 of the ASME Code Section I XI 1980 Edition with Addenda through Winter 1981 with the exception of ,

pipe welds. The extent and frequency of examinations of Class 2 pipe welds were determined in accordance with Code Case N-403 "Alternative Rules for Examination of Class 2 Piping Section XI, Division 1".

The weld selection is based on a minimum 7.5% sample (not less than 23 welds) of the total nonexempt Class 2 welds. Some of the welds though not exempt by this code case, do not require any nondestructive examination, but are included in this count to determine the 7.5% sample. t i

Selected sample welds were distributed among class 2 systems prorated, to the degree practicable. Within a system these examinations were j distributed among terminal ends, structural discontinuities and between  ;

line sizes prorated, to the degree practicable.

Table 2-3 shows a listing of the nonexempt weld count for all Class 2 1

systems.

I I i

l l

l

i my DOCUMENT NO, gy3g3 NUCLEAR ENEROY SERVICES PAGE  ;; or y V Total nonexempt Class 2 welds = 1203 d 7.5% sample of these 1203 welds = 90 welds 90 welds are selected for examination during the first !0 year interval out of a total of 1203 Class 2 welds.

TABLE 2-3 Prorated No.

System Total Welds Weld / System MS 167 167 x g = 13 RHR 618 = 46 618 x f0 3 CS 130 = 10 130 x h HPCI 9 ISS 158 x 3h = 12 RCIC SS SS x h = 6(5)*

CRD 42 9 42 x 7h = 4 Total l 1203 90 Total no. of exams to be performed in RCIC System comes out to be 6, however there are only 3 examinable structural discontinuties in this system.

2.5.3 Quality Group C l

Quality Group C components were selected for inspection in accordance with the requirements of subarticle IWD-1200 of the ASME Code Section 4

XI,1980 Edition with Addenda through Winter 1981.

I 2.6 AUGMENTED REQUIREMENTS Augmented requirements are those examinations that are specified by documents

{ }

other than the ASME Section XI code. The additional examinations required by the f ollowinc documents have been added to this procram plan.

FORM e NES 203 2180 l

DOCUMENT NO.  ?" ? m 11 NUCLEAR ENERGY SERVK;ES PAGE 05-O 2.6.1 NUREG - 0800 (Break Exclusion Piping)

For all high energy piping designated as break exclusion as defined in Appendix 3C of the Shoreham FSAR, the extent of inservice examinations completed during this inspection interval provides 100 percent volumetric examination of pipe welds within the boundary of these portions of piping, except that welds in pipe 1 inch and less nominal pipe size are exempt and socket welds will receive a surf ace examination in lieu of a volumetric examination. These welds have been added as a separate section to each system document to which they apply.

2.6.2 NUREG - 0619 l For inservice inspection an external UT examination of all feedwater nozzle safe ends, bores and inside blend radii will be performed at every l 1

second scheduled refueling outage. The sarne areas will receive a PT g examination at every ninth scheduled refueling outage (on or af ter 135 startup/ shutdown cycles). In addition the feedwater spargers will receive a visual inspection at every fourth scheduled refueling outage. These examinations are addressed in a separate section of the Reactor Pressure Vessel document (SOAS609).

2.6.3 NUREG - 0303 The Scram Discharge Volume piping has been considered class 2 piping and therefore has been subjected to the ISI requirements for class 2 piping of the Section XI.

2.6.4 NUREG - 0313 "Nonconforming Service Sensitive" welds exist at Shoreham and have been scheduled for examination at each scheduled plant outage but not more frequently than every 6 months. These welds are listed in a separate g g section of the Recirculation System (30AS612) and the Residual Heat Removal System (80AS613) documents.

FORM e NES 204 2/00

ay DOCUMENT NO. en A une 11 NUCLEAR ENEROY SERVCES PAGE ' r30 F n

/%

! ) 2.6.5 IE Bulletin 80-13 G

In accordance with the requirements of this bulletin a visual inspection of the Core Spray Spargers and the segment of piping between the inlet nozzle and the vessel shroud will be performed at each scheduled refueling outage. These inspections are listed in the Reactor Pressure Yessel document (SOAS609).

2.6.6 IE Bulletin 30 07 The Jet Pump hold down beam assemblies will receive a volumetric and a visual examination every refueling outage. These examinations are listed in the Reactor Pressure Vessel document (80AS609).

2.7 EVALUATION CRITERIA Eva!vation of reportable indications detected during the inservice inspection of Quality Group A & C (Class 1 & 3) components of the Shoreham plant shall be d

{ l made in accordance with Article IWA-3000 of the ASME Code,Section XI,1980 '

Edition, including Addenda through Winter 1981. Where as for Quality Group C (Class 2) components, the Acceptance Standards of Winter 1933 Addenda of Section XI shall be used, as required by Code Case N-408. 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.

2.3 RECORDS AND REPORTS A systern of records of the inservice inspection, plans, schedules and calibration blocks, the examination results and reports, and the corrective action required and taken, will be developed and maintained at the Shoreham site in accordance with Article IWA-6000 of the ASME Code Section XI 1980 Edition, including Addenda through Winter IfiS t.

The control of the inspection data obtained in the field shall be in accordance with the NES Inservice Inspection Program Quality Assurance Manual (80A9021) and the applicable Shoreham procedures and specifications with the following objectives:

FORM e NES 205 2/60

m DOCUMENT NO. en ^ tene I 11

\

NUCLEAR ENERGY SERVK:ES II l

/] '

(1) To insure performance of all required examinations l

(2) To provide a current indication of the status of examinations I (3) To prevent the loss of data sheets (4) To verify the completeness and accuracy of all submitted d.:ta (5) To identify and correct inspection difficulties as they are reported on the data sheets Following the completion of each inspection, a detailed summary report will be prepared as required by IWA-6220 of Section XI. The summary report shall be  !

prepared by NES and will include, as a minimum, the following details:

(1) Numbers assigned to the components by the State or Municipality, l (2) National Board Numbers assigned to the components by the manuf acturer; (3) Name of the components and descriptions, including size, capacity, material, location, and drawings to aid identification; '

(4) Name and address of manufacturers; (5) Manuf acturer's component identification nun bers; (6) date of completion of the examination or test, (7) name of Inspector who witnessed or otherwise verified the examinations, or tests, and the Inspector's employer and business address, when required; (3) abstract of examinations, or tests, performed; conditions recorded; and corrective measures recommended or taken; (9) signature of Inspector, when required; (10) Owner's Data Report for inservice inspection, Form NIS-1.

Photographs will be included where required for clarification of access or to show significant observations and/or indications.

2.9 PERSONNEL QUALIFICAT!ON REQUIREMENTS Personnel performing nondestructive examination operations shall be qualified with procedures prepared in accordance with SNT-TC-1 A and ANSI-N-45.2.6 for the applicable examination technique and methads as required by IWA-2300 of Section XI. All examinations shall be performed and the results evaluated by qualified nondestructive examination personnel.

FCAM e NES 205 2/60

, DOCUMENT NO. en mne J 11 NUCLEAR ENERGY SERVICES MGE st os 77: I O

V For nondestructive examination methods not covered by SNT-TC-1 A documents, 1

NES shall qualify personnel on the particular method involved.

The following NES procedures provide uniform programs of qualification and certification for the examination personnel for the nondestructive examination methods indicated.

1 I

l

1. SOA906S Procedure for Certifying Nondestructive Examination d Personnel.
2. 30A9069 Certification of Visual Examination Personnel.

2.10 QUALITY ASSURANCE The Quality Assurance Program to be implemented for the Shoreham inservice Inspection Program Plan is governed by three basic document sets:

(1) NES SOA9021,"Inservice Inspection Program Quality Assurance Manual",

(2) NES 30A0443, "Quality Assurance Program Plan for Inservice Inspection Progrr.m , Shoreham",

(3) The individual implementing procedures invoked by (!) and (2) above.  !

The Quality Assurance Manual defines the policies and practices employed by NES in meeting the requirements of 10 CFR 50, Appendix B. Since the Manual applies to all inservice inspection work performed by NES, it is not project- I specific.

The Quality Assurance Program Plan is specific to the preservice and inservice inspection program for Shoreham. The plan includes the detailed quality assurance requirements that are common to all phases of the program including organization, responsibility, management, liaison, project procedures and quality l I l assurance audits.

I FORM e NES 205 2/60 l

1

I my DOCUMENT NO. ememe

"" PAGE , os 3,;

  • NUCLEAR ENERGY SERVCES J i

l

3. INSERVICE INSPECTION PROGR AM PLAN DESCRIPTION l 1

l The Inservice Inspection Program Plan is comprised of this document (The General Text) and a separate document for each system. Table 3-1 is a listing of all these i system documents. Following is a generic discussion of each section of the system document.

l 3.1 SYSTEM CLASSIFICATION The Shoreham system drawings have been reviewed and Quality Group A, B & C boundaries established in accordance with Regulatory Guide 1.26.

For those systems that have Quality Group A or B components Boundary Diagrams are provided with each document to show the following:

Quality Group A nonexempt I I Quality Group A exempt Quality Group B nonexempt Quality Group B exempt Quality Group C nonexempt Quality Group C exempt For clarity all piping 1" and less has not been marked since in all cases this piping is exempt.

3.2 EXEMPTIONS Exempt areas are those areas that the ASME Code Section XI exempts from the volumetric and surf ace examination requirements. (However, they may require examination under an augmented program). All exempt components are to receive the required pressure tests. The following are the exemptions applicable to the Shoreham ISI Program.

l I FORM e NES 205 240

DOCUMENT NO, en mne ,

11 NUCLEAR ENERGY SERVCES PAGE  :: OF 20

)

C TABLE 3-1 SYSTEM DOCUMENT LIST l

Document # Title  !

l SOA3608 General Text l 30AS609 Reactor Pressure Vessel (RPV) 30A3610 Main Steam System (MS)

SOAS611 Feedwater System (FW)

SOAS612 Recirculation System (Recirc) 30AS613 Residual Heat Removal System (RHR)

SOAS 614 Core Spray System (CS) l SOAS615 High Pressure Coolant Injection System (HPCI) 30A3616 Reactor Core Isolation Cooling System (RCIC) 30A3617 Standby Liquid Control System (SLC)

SOAS613 Reactor Water Cleanup System (RWCU)

SOA3619 Control Rod Drive System (CRD)

SOAS620 Quality Group C Systems 30AS621 Containment Penetration Flued Heads l

1 l

1 l I l

FORM s NES 205 2/80

DOCUMENT NO. SO AS f;0s any PAGE 19 os 24 NUCLEAR ENERGY SERVCES l I 3.2.1 Quality Group A All reactor coolant pressure boundary components and piping 1.12 inch ID and less for all lines connected to the reactor pressure vessel below the water level and 2.24 inch ID and less for all lines connected to the reactor pressure vessel above the water level are exempt per ASME Code Section XI, IWB-1220(a),1980 Edition, Winter 1931 Addenda.

All components and piping i inch nominal pipe size and smaller are exempt per ASME Code Section XI, IWB-1220(b), 1930 Edition, Winter 1981 Addenda.

l All reactor vessel head connections and associated piping 2 inch nominal l pipe size and smaller made inaccessible by control rod drive penetrations are exempt per ASME Code Section XI, IWB-1220(c),1980 Edition, Winter 1931 Addenda.

l I 3.2.2 Quality Group B All component connections (including nozzles in vessels and pumps), piping and associated valves, and vessels and their attachments that are 4 inch nominal pipe size and smaller are exempt per ASME Code Case N-403.

All piping and other components of any size beyond the last shutoff valve in open ended portions of Systems that donot contain water during normal plant operating conditions are exempt per ASME Code Case N-40S.

3.2.3 Quality Group C Integral attachments of supports and restraints to components that are 4 inch nominal pipe size and smaller are exempt from the visual examination VT-3 per ASME Code Section XI, IWD-1220.1,1930 Edition, Winter 1931 Addenda.

FORM e NES 20$ 2/80

l

. I DOCUMENT NO. enatent l 11 NUCt. EAR ENERGY SERVCES GE - 29 0F 2e l

l l

Integral attachments of supports and restraints to components located in systems (or portions of systems) whose function is not required in support of reactor residual heat removal, containment heat removal and emergency core cooling and operate at a pressure of 275 psig or less and at a temperature of 2000F or less are exempt per ASME Code Section XI, IWD-1220.2, 1980 Edition, Winter 1981 Addenda.

3.3 EXCEPTIONS Exceptions are those areas that cannot be examined either in part or fully because of limitations in accessibility, material or design. Relief from examination for these areas will be requested from the NRC and a list of the Relief Requests will be provided in each system document.

3.4 CALIBRATION STANDARDS Table 3-2 lists all calibration standards required for the 151 program. In addition each system document lists the calibration standards required for that system.

The UT examination calibration standard design and material selection is in accordance with Subarticle 111-3400 of Appendix ill 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 ASME Code. I i

These additional reflectors are allowed by Paragraph 111-3400 of Appendis. !!! of l

the ASME Code Section XI.

l l FORM e ed$ 205 2/60

DOCUMENT NO. SOA360S yg 21 o, 24 NUCLEAR ENERGY SERVCES

/m i

V TABLE 3-7 CALORADON STANDARDS Reference Title Drawing Description Examination Area 02-160-CS 30D5013 SA-106, GR.B, 2" SCH 160 Piping Welds 2.5-OS0-CS SOC 0513 S A-106, GR.B, 2.5" SCH S0 Piping Welds 03-030-CS SOC 0513 SA-106, GR.B, 3" SCH S0 Piping Welds 04-OS0-CS SOC 0513 SA-106, GR.B, 4" SCH S0 Piping Welds 04-305-5S SOC 0513 A-376, TP 304,4" SCH SOS Piping Welds 06-030-CS SOC 0513 SA-106, GR.B, 6" SCH S0 Piping Welds 06-120-CS SOC 0519 SA-106, GR.B 6" SCH 120 Piping Welds 06-160-CS SOC 0513 SA-106, GR.B, 6" SCH 160 Piping Welds OS-100-CS SOC 0513 SA-106, GR.B, S" SCH 100 Piping Welds OS-OSO-CS LATER SA-106, GR.B, 3" SCH S0 Piping Welds

  • b 10-030-CS SOC 0513 SA-106, GR.B,10" SCH S0 Piping Welds 10-305-55 SOC 0513 AS-376, TP 304,10" SCH SOS Piping Welds

( I l 10-100-CS SOC 0519 S A-106, GR.B,10" SCH 100 Piping Welds  ;

12-040-CS LATER SA-106, GR.B.12" SCH 40 Piping Welds

  • l )

12-100-CS SOC 0513 S A-106, GR.B,12" SCH 100 Piping Welds LATER 12-STD-CS SA-106, GR.B,12" SCH STD Piping Welds

  • l 12-X X I-SS SOC 0513 A-376, TP 304,12" t = 0.633" Piping Welds 4 2-0.6SS-CS LATER S A-106, GR.B 12" SCH SO Piping Welds
  • l 14-080 CS SOC 0519 SA-106, GR.B,14" SCH S0 Piping Welds 14-100-CS SOC 0513 SA-106, GR.B,14" SCH 100 Piping Welds 14-STD-CS LATER S A-106, GR.B,14" STD. Piping Welds
  • l 16-OS0-CS SOC 0519 SA-106, GR.B 16" SCH S0 Piping Welds 16-040-CS LATER SA-106, GR.B,16" SCH 40 Piping Welds
  • l 16-100-CS 30D0520 SA-106, GR.B,16" SCH 100 Piping Welds 16-STD-CS LATER S A-106, GR.B,16" STD. Piping Welds
  • j 13-040-CS SOC 0519 S A-106, GR.B, IS" SCH 40 Piping Welds IS-100-CS SOD 0514 SA-106, GR.B, IS" SCH 100 Piping Welds IS-160-CS SOD 0514 S A-106, GR.B, IS" SCH 160 Piping Welds I S-S T D-CS LATER S A-106, GR.B. IS" STD Piping Welds
  • l

' Proposed blocks FOAM e NES 205 2<80

~

I DOCUMENT NO. SOAS603 GE U OF D l NUCt. EAR ENEROY SERVK ES o

'd TABLE 3-2 CALIBRATION STANDARDS (continued)

Reference Title Drawing Description Examination Area 20-040-CS SOC 0519 SA-106, GR.B, 20" SCH 40 Piping Welds 20-030-CS SOD 0514 SA.106, GR.B, 20" SCH S0 Piping Weld:

20-80S-55 30D0514 SA-353, TP 304 20" SCH SOS Piping Welds 20-100-CS SOD 0514 SA-106, GR.B, 20" SCH 100 Piping Welds 20-120-CS 30D0514 SA-106, GR.B, 20" SCH 120 Piping Welds 20-STD-CS LATER SA-106, GR.B 20" STD Piping Welds

  • d 22-080-55 SOD 0514 SA-333, TP 304,22" SCH SOS Piping Welds 24-040-CS SOC 0519 SA-106, GR.B. 24" SCH 40 Piping Welds 24-080-CS 80D0514 SA-106, GR.B 24" SCH S0 Piping Welds 24-305-55 SOD 0514 SA-353, TP 304, 24" SCH SOS Piping Welds 23-X X I-SS SOD 0514 S A-333, TP 304, 2S" t= 1.200" Piping Welds j } 2S-X X 2-SS 30D5015 S A-I S2, F304, 23" t= 2.6" Piping Welds CR D-BI 30D5021 Inconel 600/SA 508, CL2 CRD Return 30E0513 Nozzle Cap Weld CRD HOU/FL SOC 5014 SA-312, TP 304 CRD Housing Intermediate and Flange Weld CS-1-! A SOD 0460 S A-503, Class 2, Clad Core Spray Nozzle to j Safe End l CS-t-1B SOD 5007 inconel 600 Core Spray Safe End l C S A SOD 5003 SA-503 Class 2 Core Spray Safe End j to Extension )

C S B 30D5009 Inconel 600 Core Spray Extenstion WP SOC 0416 S A-132, F-304 WP instrument Nozzle to Safe End 3P1 SOE0415 S A-IS2, F-304/S A-50S, CL 2 Jet Pump Instrument 3005020 Nozzle Safe End l l Proposed block l

~

FCsw e NES tos ti80

DOCUMENT NO. 30A8603 O'

NUCl. EAR ENERGY SERVICES

/ \

TABLE 3-2 CALIBRATION STANDARDS (continued)

Reference Title Drawing Description Examination Area STEA M 80C0413 SA-508, CL.2 Main Steam Nozzle Transition Weld R C-IN 8000414 SA-182, F-304/SA-508, CL.2 Recirculation Inlet Nozzle Safe End RC-OUT-1 SOC 5016 SA-508, CL.2 Recirculation Outlet Nozzle R C-O UT-2 3005013 SA-132, F-304 Recirculation Outlet Nozzle N UT-3 80C0421 S A-194 Recirculation Pump Nut STUD-3 30D0420 SA-540, B23, Class 5 Recisculation Pump Stud VENT 30D0422 SA-105, GR2 Closure Head Nozzle Flange Welds Welds 131CS523 80C0425 S A 105, GR2 (G.E. Block) Feedwater Nozzle Transition Piece SNPS-71/4 GE131C7902 SA-533, Gr.B, claddea, 71/4" thick Vessel and Nozzle Welds SNPS-6 GE131C7902 SA-533, Gr.B, cladded,6" thick Vessel and Nozzle Welds SNPS-4 GE131C7902 SA-533, Gr.B, nonclad,4" thick Closure Head and Nozzle j Welds S NPS- 1.4-IR SOC 5012 S A-508, CL.2 Nozzle Inner Radius  !

S N PS-4.5- IR SOC 5012 SA-508, CL.2 Nozzle Inner Radius SNPS-7-IR SOC 5012 SA-503, CL.2 Nozzle Inner Radius SNPS-11-IR SOC 5012 SA-508, CL.2 Nozzle Inner Radius N UT-6 SOC 0419 SA-540, B-24, CL 4 Closure Head Nut STUD-6 SOC 0413 SA-540, B-24, CL4 Closure Head Stud l FL/LIG 80C0417 SA-308, CL.2 Clad RPV Flange l l FO*M a NES 205 2/80 1 1

, DOCUMENT NO. o n A 9 e n. e.

1 PAGE m OF u NUCLEAR ENERGY SERVICES " -~

(m)

, 3.5 PROGRAM PLAN AND SCHEDULE The specific examination requirements for the Shoreham Inservice Inspection Program are defined by the Program Plan and Schedule. This Program Plan lists all the examinations required by Tables IWB-2500-1, IWC-2500-1 and IWD-2500-1 of Section XI to be completed in the first inspection interval (10 years).

The plan includes the component identification and description, ASME Code Section XI examination category, code examination method (visual, surface and/or ultrasonic), examination procedure number and, where applicable, a calibration block number.

In the Program Plan, each weld or other examination area has been given a unique identification number. The numbering system for the welds and components are identical to Stone & Webster, General Electric and Dravo designations. The RPV-related welds ar.d parts have been designated v ith numbers originally assigned by Combustion Engineering. When weld numbers

{ } were not available, a number was assigned by NES for this program.

The Program Plan and Schedule containing the examinations required in the first interval, has been subdivided into three periods. By completing all the examinations in the periods for which they are listed, the program will meet the requirements of the Section XIInspection, Program B.

j NOTE: Longitudinal welds on Main Steam and Recirculation piping and fittings are j designated with the suffixes "U" (Upstream of the reference

{

circum ferential weld) and "D" (Downstream of the reference circumferential weld). In case of double-sided fittings, "Ul" and "Dl" denote longitudinal welds on the long side of the component. I 3.6 ISOMETRICS AND SKETCHES The isometrics and sketches show the physical location and identification numbers for all examination areas. Valves, pumps and penetrations have also been identified by their Stone and Webster numbers, with elevations and flow

{ } directions. Ali isometrics and sketches were generated from the listed reference drawings.

FCAM sNES 205 2/B0 l

Retrieved from "https://kanterella.com/w/index.php?title=ML20196A841&oldid=2987687"