ML20196A960

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Rev 2 to 80A8619, Inservice Insp Program Plan,Crd Sys, Shoreham Nuclear Power Plant Unit 1
ML20196A960
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
80A8619, NUDOCS 8802050218
Download: ML20196A960 (19)
v • d • e


Text

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I DOCUMENT NO. 80A8619 REV. 2 NUCLEAR ENERGY SERVICES PAGE. I OF 7 l

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'd INSERYlCE INSPECTION PROGRAM PLAN CONTROL ROD DRIVE SYSTEM j SHOREHAM NUCLEAR POWER PLANT l UNIT 1 l l

Prepared For

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DOCUMENT NO. RO A R A 19 m

1 NUCLEAR ENERGY SERVICES PAGE 2 OF 7 l l l

1 TABLE OF CONTENTS l

i PAGE 1 1

1

1. INTRODUCTION 4 l l
2. CLASSIFICATION 4
3. EXEMPTIONS 4 i
4. EXCEPTIONS 5 l
3. CALIBRATION STANDARDS 5 9 6. PROGRAM PLAN AND SCHEDULE 5
7. PRESSURE TESTS 6
8. ISOMETRIC FIGURES AND SKETCHES 7
9. AUGMENTED REQUIREMENTS 7 Tables 3-1 Exemptions 4 4-1 Exceptions 5 5-1 Calibration Standards 5 6-1 Section XI Examination Schedule 6 8-1 Isometric Figures )

7 '

Appendix A I O

FORM s NES 205 2/80 l l

4 DOCUMENT NO. 80A3619 mur M 8F NUCLEAR ENERGY SERVCES l I

1. INTRODUCTION This document presents the Inservice Inspection Requirements for the Control Rod  ;

Drive System of the Shoreham Nuclear Power Plant.

i The General Text, NES Document Number 80A8608 presents the basis for the Inservice Inspection Program and a more detailed description of the Inservice Inspection l

Program Plan than is contained in this document.

I

2. CL ASSIFICATION l

The Control Rod Drive System piping and instrumentation diagrams have been reviewed and Quality Group B boundaries have been established in accordance with Regulatory Guide 1.26 Rev 3. These boundaries are shown on Figure FM-278-ISI. l

3. EXEMPTIONS S The portions of the Control Rod Drive System that are exempted from the volumetric and surface examinations of Section XI are listed in Table 3-1.

l TABLE 3-1 EXEMPTIONS Quality Component Basis for Boundary Group Description Exemption Diagram B All piping 4 inch Code Case F M-27B-ISI d nominal pipe size N-408(b)(1) and smaller O

FORM

  • NES 205 2180

(

80A8619 DOCUMENT NO. .

" l 1 NUCLEAR ENERGY SERVCES 5

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4. EXCEPTIONS i

For those examinations in the Control Rod Drive System that cannot be completed in  ;

accordance with the Section XI requirements a relief request will be prepared and submitted to the NRC. Those areas for which a relief request has been prepared are listed in Table 4-1.

l TABLE 4-1 i EXCEPTIONS l

Component Component Fig. Relief l Identification Description No. Request Remarks )

l None

5. CALIBRATION STANDARDS O Table 5-1 lists the Calibration Standards for ultrasonic examinations scheduled for the 1

Control Rod Drive System.

TABLE 5-1 CALIBRATION STANDARDS Title Size Material Drawing l l

08-080-CS 8" SCH.80 SA-106, GR. B Later b

6. PROGRAM PLAN AND SCHEDULE The specific Control Rod Drive 151 examination requirements are defined by the Program Plan and Schedule Tables. This Program Plan lists all the required examinations for a 10 year interval of 3 periods of 40 months each. Table 6-1 presents a summary of these Section XI required examinations scheduled by different Code categories applicable to this system.

FCRM 8 NES 205 2/80

l 0A8619 DOCUMENT NO.

NE OF

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  • NUCLEAR ENERGY SERVICES Each weld and component is designated by a unique identification number, and then described. Also identified is the applicable examination procedure, Code category and number, examination method, and the calibration block, if required. Any comments specific to a component are noted in the remarks column.

Examination items are divided according to the Isometric figure on which they appear and are listed following the direction of flow in the pipe. Multiple examination requirements of the same component are listed together in the schedule tables.

TABLE 6-1 SECTION XI EXAMINATION SCHEDULE  :

CONTROL ROD DRIVE SYSTEM Examinations by Component Code Period Total In Description Category Pi P2 P3 Total System  :

O 1 Piping Welds C-F-2 1 1 2 4 42 b (circumferential)*

System Leakage Test C-H 1 1 1 3 -

System Hydro Test C-H 0 0 1 1 -

7. PRESSURE TESTS In accordance with Section XI all Quality Group B pressure retaining components are to receive a leakage test every Period (40 months) and a hydrostatic test once during the interval (10 year). The leakage test is to be done in accordance with IWC-5221 and the hydrostatic test in accordance with IWC-5222. The portions of the Control Rod Drive system requiring these pressure tests are those marked Quality Group B including lines 1 inch and less on boundary diagram FM-27B.

O FORM s NES 200 2/80

80A8619 DOCUMENT NO.

7 7 WW W NUCLEAR ENERGY SERVICES l l

8. ISOMETRIC FIGURES AND SKETCHES The piping isometric figures listed in Table 8-1 show the identification and location of areas for the Control Rod Drive System requiring examination. Sketches may also be included that illustrate or locate areas of components requiring identification for examination. Boundary Diagrams are provided to show the Quality Group boundaries and also to define those areas requiring pressure testing under Code Category C-H.

TABLE 8-1 ISOMETRIC FIGURES 8619-1 Rev. 0 8619-2 Rev.0 BOUNDARY DIAGRAMS 4

FM-27B-ISI Rev.0

9. AUGMENTED REQUIREMENTS l

l Following are the augmented requirements that apply to the Control Rod Drive System.

9.1 NUREG-0803 l As required by NUREG-0803 the scram discharge volume is being examined in accordance with the ISI requirements for class 2 piping in accordance with Code' Case N-408, d

9 FOAM e NES 205 2/80

O APPEND /X A O

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l 1

80AS619

., DOCUMENT NO.

PAGE OF.

l NUCLEAR ENERGY SERVICES, INC.

APPENDIX A Table of Contents Number of Pages

1. Program Plan Work Schedule Tables Period 1 1 Period 2 1 Period 3 1
2. Isometric Figures 8619-1 I l 8619-2 1
3. Boundary Diagrams FM-27B-ISI 1

I FORM s NES 205 2/80

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O O O SHOREHAM NUCLEAR POWER. STATION SYSTEM: CONTROL ROD DRIVE ISI PROGRAM PLAN AND SCHEDULE PEFIOD 1 NES ISO NUMBER 8619-1 80A8619 REV. 2 PAGE 1 OF 1.

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1 COMPONENT l SIZE I COMPONENT l PROC. I CAL. I CODE I CODE IEXAM I REMARKS I I IDENTIFICATION 1 (IN) I DESCRIPTION 1 NO. I BIDCK I CAT. I NO. IMEIH I  !

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O O O SHOR& LAM NUCLEAR POWER STATION SYSTEM: CONTROL ROD DRIVE ISI PROGRAM PLAN AND SCHEDULE PERIOD 2 NES ISO NUMBER 8619-1 80A8619 REV. 2 PAGE 1 0F 1 I I I I I I I IQDE I I I COMPONENT l SIZE I COMPONEKr i PROC. I CAL. 1 00DE l 00DE IEXAM i REMARKS I I IDENTIFICATION l (IN) l DESCRIPTION I NO. I BLOCK I CAT. I NO. IMEni I I I I I I I I I I I I

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O O O SHOREHAM NUCLEAR POWER STATION SYSTEM: CONTROL ROD DRIVE ISI PROGRAM PLAN AND SCHEDULE PERIOD 3 .

NES ISO NUMBER 8619-2 80A8619 REV. 2 PAGE 1 0F 1 I I I I I I I ICODE l l 1 COMPONENT I SIZE I COMPONEhT l PROC. I CAL. 1 CODE I CDDE lEXAM I REMARKS I i IDENTIFICATION I (IN) l DESCRIPTION l NO. l BIDCK  ! CAT. I NO. IME111 l l I 1  ! I I i I i l 1 C11-IC-3028.-W-7 8 PIPE 10 TEE 80A3131 08-080-CS 80A3132 C-F-2 C5.51 Ur PT g

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