ML20009E895

2 to Preservice Baseline Insp Program for Facility

ML20009E895
Person / Time
Site:	Sequoyah
Issue date:	06/18/1981
From:	Belew, Daniels, Gorman D TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20009E885	List: ML20009E884 ML20009E895
References
SI-114, NUDOCS 8107280527
Download: ML20009E895 (4)

Text

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ENCLOSURE a

Sequoyah Nuclear Plant DISTRIBUTION IC Plant Master File

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Plant Superintendent ts Assistant Plant Supt. (Oper.)

SURVEILLANCE INSTRUCTION Assistant Plant Supt. (Maint.)

Assistant Plant Supt. (H&S) f Administrative Supervisor SI-114 1C Maintenance Supervisor (M)

IC Assistant Maintenance Supervisor (M)

Maintenance Supervisor (E)

Assistant Maintenance Supervisor (E)

PRESERVICE BASELINE INSPECTION FOR Maintenance Supervisor (I)

TENNESSEE VALLEY AUTHORITY IU Results Supervisor SEQUOYAH NUCLEAR PLANT IC Operations Supervisor

\\c-Quality Assurance Supervisor d

Health Physics Supervisor Public Safety Services Supv.

i Chief Storekeeper Preop Test Program Coordinator

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Units 1 & 2 IC Outage Director l

Chemical Engineer (Resul'ts)

Radiochem Laboratory Instrument Shop Reactor Engineer (Results)

Instrument Engineer (Maint. I)

_) C Mechanical Engineer (Results)

IU Plant Services Supervisor IC Training Center Coordinator i, Prpared By:

Belew/Daniels Public Safety Services SNP L

Revised By:

Shift Engineer's Office Dan Gorman 1C Unit Control Room Health Physics Laboratory Submitted By:

v0 ^#l&,1 lu Nuc1r Document Control unit-C q.

-Supervisor IU Pwr Plant Superintendent, WBNP Pwr Plant Superintendent, BFNP PORC Review:

4, g j/a j Pwr Plant Superintendent, BENP Batt IU NEB-K NRC-IE:II Approved By:

,m ( N Resident NRC Inspector SNP Plant Manager 1C NSRS-K Technical Support Center Date Approved:

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IC Unit Control Room #2

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IU Compliance Section Staff Supervisor IU QCRU - CONST SNP 1U Project Manager, Seq.

IU _ Supv. Codes and Standards Sect.-C IU Stup, Metalurgy & NDT Section, 505 EB-C Rev. No.

Date Revised Pages Rev. No.

Date Revised Pages 11 4/21/81 ALL 12 6////B/

3,5,27

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The.last page of this instruction is Number 221

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8107280527 010721

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PDR ADOCK 05000327 G

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.J SQNP.

SI-114 7

Page 1 of 32 j

Rev.-12 s

1.0 STATEMENT OF APPLICABILITY This program outlines details for performing the preservice nondestructive examinations of the Sequoyah Nuclear Plant ASME Code Class 1, 2, and 3 com-j 1.,nents (and their supports). The program has been organized.to fulfill i-

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prese.vice examination requirements of the Sequoyah Operational Quality Assurance Manual, Part II, Section 5.1 and comply as practical with the

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requirements of Section XI of the ASME Boiler and Pressure Vessel Code.

In accordance with 10 CFR Part 50, 50.55a(g)(1), a preservice inspection is r.o t. required for Sequoyah. However, the areas outlined in this program to receive a preservice inspection will be examined.

The requirements of.

ASME Section XI are in effect when the requirements of the applicable con-struction code have been satisfied.

The requirements of this program are in effect until unit commercibi operation.

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y -Beginning with unit commercial operation, the requirements of the Inservice 4

Inspection Program are applicable in accordance with 10 CFR 50 section 50.55 (g) (4) (i) and section 50.55 a (g) (4) (iv).

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Specifics concerning performance of. nondestructive examinations are not a part of this program, but are included in nondestructive examination

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procedures (DPM N80E3 and SNP TI-51).

2.0 PURPOSE

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'J The Preservice Inspection Program (hereinafter PSI) is preliminary in nature and is employed to obtain detailed information for inclusion. in the Inservice Inspection Program. The examinations required by.this l.

'l program will establish acceptance of components for service..In addition, this program partially satisfies the preservice requirements of SR 4.0.5, 4.4.5, and 4.4.10.

The PSI Program serves as a means of determining built-in limitations caused by original plant design, geometry, materials of construction of the components, and the current technology or state-of-art -of nondestructive testing. The PSI Program will also permit verification of the examination methods selected, finalization of detailed procedures, and will establish preservice examination data to be used as a reference for later-inservice-j examinations.

2 3.0 CODES OF RECORD 1

This program w^as prepared to meet the requiremei..s of the 1974 Edition, Summer 1975 Addenda of Section XI of ASME Boiler and Pressure Vessel Code.

3 Criteria for determining Class 2 pressure retaining bolting subject to

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examination is in accordance with the 1977 Edition, Summer 1978 Addenda of Section XI.

Criteria for determining components subject to system pressure tests following repair by welding is in accordance with the

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Summer 1978 Addenda of Section XI.

Procedures-for Eddy Current Examination

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9 of heat exchanger tubing, which the Summer 1975 Addenda of ASME Section XI has no provisions for, meets the requirements of the 1974 Edition, Summer

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1976 Addenda of ASME'Section XI.

Steam generator tubing examination require-ments'are in accordance with Regulatory Guide 1.83, Rev.

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L SQNP SI-ll4 Page 3 of 32 Rev. 12 Certain examinations performed in shop and/or by CONST will be identified by the Metallurgy and Standards Group and employed to serve for the ASME Section XI PSI.

In these instances, a member of the NCO QA Staff may perform a random sample review of CONST data packages and/or may obtain shop records to assure that examinations have been performed. CONST

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c....._-' ~ nrocedures may be obtained by the NCO QA Staf f for reference.

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Whenever inspection requirements are being accomplished under the juris-

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t diction of NUC PR, a NCO QA Staff representative shall be onsite to coord-inate activities. He will be the designated TVA representative to ensure g

contract compliance and to ensure proper disposition of needed procedure changes to both TVA and/or contractor procedures in accordance with approved vendor QA program and Section 6.3, Part II of the 0QAM.

Additionally, the NCO QA Staff representative will be responsible for),

notifying the Plant Manager of all unacceptable indications as soon a's L

practical. Whenever an unacceptable indication is discovered, the procedure and form in Appendix D shall be utilized.

In those cases where an outside contractor is furnishing preservice examination services, it will be the responsibility of the contractor to initiate the form in Appendix D under the supervision of the NCO QA Staff representative.

See section 16.0 of this program, i.

As examinations are completed, the NC0 QA Staff representathe shall sign for completion the appropr' ate sections of Data Sheet 2 in Appendix C of this program. When all examinations of this progran have been completed, m

Data Sheet 2 shall be signed for completion by the NCO QA Staff represen-

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tative and reviewed by the Supervisor, Baseline and Inservice Inspection

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Section, QA Staff.

In the event system or component alterations or repairs are made which require component reexamination, or components are re-examined for other reasons, following signoff of Data Sheet 2,- the appropriate sections of Data Sheet 3 in Appendix C shall be completed and signed by the NCO QA Staff representative.

(The requirements of this paragraph pertain to unit 2 only.)

1 All preservice examinations should-be completed prior to initial plant start 2p (Operational Mode 2). Prior to initial plant startup, Data Sheet 3, in addition to Data Sheet 2, in Appendix C shall be signed by the NCO QA Staff representative and reviewed by the Supervisor, Baseline and Inservice i

Inspection Section, QA Staff and the Supervisor, Codes and Standards Section of the Metallurgy and Standards Group. The Plant Manager shall approve the data package (Data Sheets 1, 2, and 3) by signing Data Sheet 1.

These data sheets shall be filed at the plant site with PSI examination data and final reports discussed in Section 15.0 of this program.

(The requirements of this Paragraph pertain to unit 2 only.)

m PSI program preparation is the responsibility of Metallurgy and Standards l

Group of the Controls and Test Branch. Any revisions initiated by other groups shall be submitted to the Metallurgy and Standards Group for informal approval prior to incorporating the revisions into this program.

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SQNP SI-ll4 Page 25 of 32 Rev. 12

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11.5 Volumetric Examination (Ultrasonic) 1 l

Ultrasonic examination shall be conducted in accordance with the provisions of Appendix I of Section XI of the ASME Code.

Where Appendix I (I-1200) is not applicable, the provisions of Article t -

5 of Section V of the ASME Code shall apply.

11.6 Volumetric Examination (Eddy Current)

Eddy current examination of heat exchanger tubing shall be conducted 4

in accordance with the provisions of Appendix IV of Section XI of the 1

ASME Boiler and Pressure Vessel Code (Summer 1976 Addenda).

12.0 QUALIFICATIONS OF NONDESTRUCTIVE EXAMINATION PERSONNEL i

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Personnel performing nondestructive examination operations shall bei qualified in accordance with IWA-2300 of ASME Section XI (DPM N75C01).

CONST personnel which perform visual examinations in accordance with this program need not bc gualified in accordance with IWA-2300.

13.0 ACCEPTANCE CRITERIA All acceptance standards for Class A, B, C, and D components shall i_

be in accordance with IWA-3000 of ASME Section XI.

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14.0 REPAIRS AND REPLACEMENTS 7 Repairs shall be made in accordance with ASME Section XI or in accordance with the Design Specification and Construction Code of the component or system.

-t y Later editions of the Construct...n Code or Section III, either in its y extirety, or portions thereof, may be used.

After repairs by welding on the pressure-retaining boundary of components, a pressure test shall be performed in accordance with IWA-5000 and IWB-5000, IWC-5000, or IWD-5000 as applicable of ASME Section XI.

The following may be exempted from these pressure tests exclusive of those repairs employing a temper bead technique:

(1) Cladding repairs (2) Heat e:: changer tube plugging (3) Piping, pump, and valve repairs that do not penetrate through the pressure boundary h*

pg.

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