ML20092C779

1984 Remote Visual Exam of Core Spray Sprarger Sys of Pilgrim Nuclear Power Station,Unit 1, Final Rept

ML20092C779
Person / Time
Site:	Pilgrim
Issue date:	05/31/1984
From:	Dwigans J, Flach W SOUTHWEST RESEARCH INSTITUTE
To:
Shared Package
ML20092C775	List: BECO-84-085, Forwards Final Rept, 1984 Remote Visual Exam of Core Spray Sparger Sys of Pilgrim Nuclear Power Station,Unit 1, Per IE Bulletin 80-13 & Util .Exam Revealed No Change in Conditions Reported During 1981 Exams ML20092C779
References
NUDOCS 8406210321
Download: ML20092C779 (75)

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1984 REMOTE VISUAL EXAMINATION OF THE CORE SPRAY SPARGER SYSTEM OF PILGRIM NUCLEAR POWER STATION, UNIT 1 FINAL REPORT SwRI Project 7861 Prepared for Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199 May 1984 h

==R SOUTHWEST RESEARCH INSTITUTE

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1984 REMOTE VISUAL EXAMINATION OF THE CORE SPRAY SPARCER SYSTEM OF PILGRIM NUCLEAR POWER STATION, UNIT 1 FINAL REPORT SwRI Project 7861 Prepared for Boston Edison Company 800 Boylston Street Boston, Massachusetts 02199 i

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May 1984 I

Prepared by Approve by U

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J. L. Dwigan's

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Inspection Engineering Section Departm t of Engineering Services Quality Assurance Systems and Engineering Division t

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ABSTRACT A remote visual examination of the Core Spray Sparger system of the reac-tor pressure vessel (RPV) of Boston Edison Company's Pilgrim Nuclear Power Station, Unit 1, was performed during the 1984 refueling outage. This was the third examination of this type performed on the core spray sparger system and the first performed during the second 10-year interval of com-j mercial operation. The areas examined included the reactor vessel core spray piping and spargers.

j The examinations revealed no apparent change in the conditions reported during the 1981 examinations. No other areas of concern were identified.

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r TABLE OF CONTENTS Page LIST OF ABBREVIATIONS.

iv I.

INTRODUCTION.

1 A.

Applicable Documents 1

B.

Examination Areas.

1 C.

Summary of Examination Results 1

II.

DETAILS OF THE INSERVICE EXAMINATION.

3 A.

Equipment 3

B.

Radiation Exposure 3

C.

Explanation of Field Data Records.

3 D.

Summary of Nondestructive Examinations 3

APPENDICES A.

Southwest Research Institute Nuclear Projects Operating Pt 'edures B.

Southwest Research Institute Nondestructive Testing Procedure C.

Certificates of Personnel Qualifications D.

Nur. lear Regulatory Comuission Inspection and Enforcement Bulletin No. 80-13 E.

Relook Results - 2/24/84 FIELD DATA Core Spray Sparger A Core Spray Sparger B Core Spray Sparger C Core Spray Sparger D Core Spray Piping iii

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LIST OF ABBREVIATIONS American Society of Mechanical Engineers ASME Boston Edison Company

-BECo Customer Notification Form CNF Inservice Examination ISI NDT Nondestructive Testing Nuclear Regulatory Commission NRC Quality Assurance QA RPV Reactor Pressure Vessel Southwest Research Institute SwRI Visual Examination VT

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I.

INTRODUCTION During the 1984 refueling outage, Southwest Research Institute (SwRI) per-sonnel performed remote visual (VT) examinations of the Core Spray Sparger system in Boston Edison Company's (BECo) Pilgrim Nuclear Power Station, Unit 1.

This examination was a follow-up to the January 1980 and October 1981 examinations and was performed to meet the intent of the Nuclear Regu-latory Commission Inspection and Enforcement Bulletin No. 80-13.

A.

Applicable Documents The examinations were performed in accordance with the following documents:

Section XI of the American Society of Mechanical Engineers (ASME)

Boiler and Pressure Vessel Code, " Rules for Inservice Inspection of Nuclear Power Plant Components," 1980 Edition, with Addenda through Winter 1980. In addition, the examination addressed the requirements of the Inspection and Enforcement Bulletin 80-13 and provided visual resolution of a 0.001-inch diameter wire placed in the examination area.

SwRI Project Plan for the 1984 Inservice Remote Visual Examina-

. tion of Core Spray Spargers at Pilgrim Nuclear Power Station, Unit 1.

B.

Examination Areas As a continuing observation of the indications detected during the January 1980 and October 1981 outages, accessible portions of the follow-ing components and areas were examined using remote VT techniques.

Reactor Pressure Vessel Core Spray Sparger A Core Spray Sparger B Core Spray Sparger C Core Spray Sparger D Core Spray Piping The remote VT examinations were conducted in accordance with SwRI Non-destructive Testing (NDT) procedure 900-7, Rev. 6, which was written to conform to the requirements of the applicable sections of the ASME Boiler and Pressure Vessel Code and the SwRI Nuclear Quality Assurance Program Manual. A copy of this SwRI NDT procedure is included in Appendix B.

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C.

Summary of Examination Results The interpretation of the examination results was performed in accor-dance with the SwRI Examination Plan prepared for Project 17-7861. The

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I resulting data (video tapes) was evaluated by a Level III visual examiner, qualified by experience and written examination. Reexamination was accomplished as considered necessary to resolve the various types of indications.

SwRI operating procedures applicable during the examinations are included in Appendix A.

The remote VT examinations revealed numerous insignificant indica-tions. The indications in the Core Spray Sparger Piping were determined to be of the same magnitude as the previously reported indications. These indications appear to have stabilized with respect to crack propagation and further degradation is not anticipated. As with the previous examina-tions, several examination areas were limited because of structural interference.

A number of typical indications were selected for reexamination to provide added assurance that the general interpretations were correct.

Thase indications were recorded and labeled "Relooks." A brief descrip-tion of the relook results is included as Appendix E.

The previously identified area which includes the B junction box-to-pipe weld on the 0* side and extends to and including the first spray

, nozzle (No. 25) was specifically reexamined. There has been no apparent change since the October 1981 examination. No other areas of concern were identified.

There has been no observable change in the sparger condition since the October 19ol examination.

Examination personnel were certified in accordance with SwRI Nuclear Quality Assurance Procedures 11-1 and 11-2 which incorporate the guidelines of SNT-TC-LA of the American Society for Nondestructive Testing. A copy of each individual's certification is included in Appendix C.

Appendix D contains a copy of the Nuclear Regulatory Commission Inspection and Enforcement Bulletin No. 80-13.

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II.

DETAILS OF THE INSERVICE EXAMINATION j

This section of the report provides a discussion of the equipment used and radiation exposure encountered during the inservice inspection (ISI), an explanation of field data records, and a summary of the nondestructive exam-inations performed.

A.

Equipment A remote video system, with cameras provided by BECo and manipulation equipment by Consulting Personnel Services, Inc., was used for the VT exam-inations. Certain portions of the video tape recorded data were computer enhanced to improve resolution. The video enhancement equipment was pro-vided by APTEC Imaging, Inc.

B.-

Radiation Exposure Radiation exposure encountered during the examinations was of funda-mental concern to all SwRI personnel involved during the daily examination activities. SwRI personnel took the necessary precautions in order to minimize overall exposure and consequently received the minimum dosage practicable while performing the examinations. The radiation level on the refueling crane, where the examination personnel were primarily located, 4

was approximately 15. mrem per hour.

C.

Explanation of-Field Data Records The results of the examinations performed by SwRI personnel were recorded on standard SwRI forms. These completed documents constitute a portion of the ISI report. The original records are retained in the SwRI Data Storage Facility, and copies are provided herein for completeness.

The Visual Examination Record Sheets for each examination area are assembled into a package preceded by a Summary Sheet. The examination areas and summary sheet numbers correspond to those listed in the Summary Table. These record sheets were used.to record the results of the examina-tions. Also, the material used in the examinations is identified on the sheets.

D.

Summary of Nondestructive Examinations The following section of this report is the Summary of Nondestructive Examinations Table (Summary Table). The Summary Table provides information and results for the nondestructive examinations performed during this remote VT examination. See Figure 1 for an explanation of the Summary Table format.

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S A$asE ASME

$-48 WE4O INDIC MtONS retOCEDunE EMAas Sune REMARKS SE C. ma aEC. XI A

t tE ns NO CAIGV 9eOJUtEV.

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The reserke celues to used to describe any pertiment feature of the esamtmaties such se lleitations, 4

j reportable resulte, CNFe. etc.

1 Ultremonte cattbration blocke are eleo listed here.

The presence of indicat tone elitch are deemed reportable to the customer to In-dicated in thle column.

He presence of ultrasonic Indications shown to be the results of a geometric feature of the esset-matten area le indicated in thte column.

k H e presence of nonrelevant indications or ultramonte indicatione attich are equal to er greater then recording amplitude but less then evaluettoe level de indicated in thle column.

l Me absence of ladicattens equal to or greater than alie recording level of the respective IIDT procedure to sedicated in thle column.

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nie column references the eneminetton summary sheet whicIs serves se a cover sheet for the date package and liste glie date record numbers, the esaminers, and any pertinent 6

remarks.

his colimes liste the applicable seal HDT procedure used for time essetnet ton.

The IIDT nethod mord during the examinetton to listed in thle column.

1 Each eseelsatten eres to Itated in thte column. peLatte of the weld identification system are contained in Appendices A and B.

He A$ttE Section El flee neer and category of the enaninetton area ese listed in these colussee.

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Figure 1.

Explanation of Summary Table Format

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' PIIERIN NUCLEAR POWER MATICII, tmlIT 1 i

1984 IllSERVICE RENDTE VISUAL EXAMINATICIOS REACTOR PRESSURE VESSEL ASME ASME EXAMeNATION EXAM' SEC Mi SEC. XI PROCEOURE E XAM. SUM.

REMARKS

. AREA 80ENTIFICATION METHOO ITEM NO.

CATGY.

NO/REV.

SHEET NO.

NO RECOROASLE INSIGN6FICANT GEOMETRIC OTHER VESSEL INTERIOR 813.20 4-N-2 Sparger A VT-1 900-7/6 786101 X

Examination of Sparger "A".

(Upper Sparger) including retook of 1981 indi-cation areas. revealed all indications to be insignificant.

B13.20 B-N-2 Sparger B VT-1 900-7/6 786102 I

Emanination of Sparger "B",

1 (lower Sparger) including relook of 1981 indi-I cation areas at 345' (O' side),

weld, and Nozzle 525 show no observable change. No other significant indications.

Bl3.20 B-N-2 Sparger C VT-1 900-7/6 786103 I

Examination of Sparger "C".

(Upper Sparger) including relook of 1981 indi-cation areas, revealed all j

indications to be insignificant.

B13.20 B-N-2 Sparger D VT-1 900-7/6 786104 X

Examination of Sparger "D".

i (lower Sparger) including relook of 1981 indi-cation areas, revealed all l

indications to be inafgnificant.

Bl3.20 8-N-2 Core Spray Piping VT-1 900-7/6 786105 I

Examination of the Core Spray i

VT-3 Piping including piping support brackets, revealed all indica-l tions to be insignificant.

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APPENDIX A SOUTlWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURES

APPENDIX A SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURES Table of Contents ProcedureNo.fRev.

Title IX-FE-101-2 Deviations to Nuclear Projects Operating Procedures X-FE-101-2 Onsite NDE Records Control XIII-AG-101-2 control of Nuclear Inspection Equipment and Materials XVII-AG-101-1 Data Storage and Retrieval Change 1 I.

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SOUTHWEST RESEARCH INSTITUTE IX-FE-101-2 NUCLEAR PROJECTS j

October 1981 OPERATING PROCEDURE Page 1 of 6 Title DEVIATIONS TO NUCLEAR PROJECTS OPERATING PROCEDURES EFFECTIVITY AND APPROVAL Revision 2 of this procedure became effective on Nov. 2. 1981 This procedure consists of the pages and changes listed below.

Page No Change Date Effective 1 through 6 November 2, 1981 l

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Approvals Written By Date Technical Review Date f/

Manager of Q.A.

Date Cogn t Director Date l}

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1 SOUTHWEST RESEARCH INSTITUTE Im-o -2 l

October 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 6 1

DEVIATIONS TO NUCLEAR PROJECTS OPERATING PROCEDURES l

1.0 PURPOSE 1.1 The purpose of this operating procedure is to establish guidelines and controls for deviations to Nuclear Projects Operating Proce-l dures.

2.0 SCOPE AND APPLICATION 2.1 This procedure applies to Nuclear Projects Operating Procedures.

2.2 Deviations written in accordance with this procedure shall be applicable only to the specified plant and examination area described in the Procedure Deviation, SwRI Form FE-4-3 (sample attached).

2.3 Deviations written in accordance with this procedure do not con-stitute permanent changes or revisions to the applicable pro-cedures.

2.4 This procedure meets the requirements of SwRI Nuclear Quality Assurance Program Manual (NQAPM).

3.0 RESPONSIBILITY 3.1 The Director of the Department of Engineering Services, or his designated altirnate within the Quality Assurance Systems and l

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Engineering Division, shall be responsible for the initiation of l

this procedure.

l 3.2 Qualification of deviations to operating procedures shall be the responsibility of the Director of the Department of Engineering Services, or his designated alternate.

l 3.3 The Assistant Manager of the Technical Activities Group, Team Supervisor, or other cognizant persons using the procedure shall i

l be responsible for initiating the request for a deviation to the l

operating procedure.

3.4 The Department Director, or his designated alternate, shall be responsible for approval of operating procedure deviations.

3.5 The Manager of Quality Assurance, or his designated alternate, shall be responsible for reviewing and approving proposed devia-tions to operating procedures against the requirements of this procedure.

Sam Form o4 3 2-

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SOUTHWEST RESEARCH INSTITUTE u-rz-lol-2 i

October 1981 NUCLEAR PROJECTS OPERATING PROCEDURE As,

4.0 PROCEDURE 4.1 The Assistant Manager of the Technical Activities Group, Team Supervisor, or other cognizant persons who require a deviation to a Nuclear Projects Operating Procedure shall be responsible for initiating a Procedure Deviation, SwRI Form FE-4-3.

Deviations may be required due to changing technology, applicable code changes or interpretations, plant or component design, customer requirements, or special cases.

If the procedure deviation is initiated by a telephone call from the field, and the requestor is not available to sign the request, his name shall be typed in the " Requested By" block.

4.2 The Assistant Director of the Department of Engineering Services, or his designated alternate, shall assign responsibility for pre-paring the procedure deviation.

4.2.1 The Procedure Deviation, SwRI Form FE-4-3, shall have, but not be limited to, the following information:

(1)

Site (2)

Procedure Number (3)

Procedure Section and Page (4)

Deviation Number l

(5)

Date Requested 1

(6)

Examination Area (s) and Specific Outage Affected by Deviation (s) l (7)

Deviation Required i

(8)

Justification for Deviation (s).

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4.2.2 Deviation numbers shall be assigned by the Manager of the Support and Administration Section, or designated alter-nate, and shall be in numerical sequence beginning with "1" for each procedure revision.

4.3 The procedure deviation shall be qualified by either field use, laboratory verification, or review by a qualified Level III individual, under the direction of the Director of the Department of Engineering Services or his designated alternate.

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SOUTHWEST RESEARCH INSTITUTE IX-FE-101-2 October 1981 NUCLEAR PROJECTS OPER ATING PROCEDURE I

Page 4 of 6 4.4 Upon qualification in accordance with Paragraph 4.3, and veri-fication that the procedure deviation is in compliance with the applicable code /other requirements, the person conducting the technical review shall sign the deviation.

4.5 The Manager of Quality Assurance, or his designated alternate, shall verify that the deviation is in compliance with this proce-dure and sign the procedura deviation as reviewed and approved and forward it to the Department Director, or his designated alter-nate.

4.6 If approved, the Department Director, or his designated alternate, shall sign the procedure deviation and forward it to the' Support and Administration Section for reproduction, cop} distribution, and filing of the original document.

-4.7 The final deviation shall carry the signatures as follows:

(1)

Requested By.

Requestor, if available to sign. If he is i

not available, his name shall be typed in the " Requested By" block.

(2)

Technical Review. A technical review shall be conducted by a person having an adequate understanding of the requirements and intent of the deviation, who does not administratively report to the author, and is a represent-ative of the same group that performed technical review of the affected procedure.

c (3)

Approved By.

Manager of Quality Assurance, or his I

designated alternate.

(4)

Approved By.

Department Director, or his designated alternate.

4.8' The requesting team supervisor any use the Procedure Deviation of I

the Nuclear Projects Operating Procedure upon receipt of the final approval and site approval of the deviation.

l-4.9 The deviation number shall be recorded in conjunction with the appropriate Nuclear Projects Operating Procedure number on all records requiring the recording of the procedure number.

4.10 A copy of the Procedure Deviation, SwRI Form FE-4-3, shall be attached to the applicable procedure when conducting examinations in accordance with the deviation.

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SOUTHWEST RESEARCH INSTITUTE IX-FE-101-2 October 1981 NUCLEAR PROJECTS OPER ATING PROCEDURE

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Page 5 of 6 5.0 RECORDS 5.1 Operating prceedure deviations and any other documents generated in accordance with this procedure controlling the performance of onsite critical services shall be retained for the period spec-ified in the contract with the Client. These records shall be indexed, filed, and maintained in the Data Storage Facility of the Quality Assurance. Systc=a and Engineering Division.

5.2 A copy of the approved Procedure Deviation, SwRI Form FE-4-3, shall be forwarded to the Manager of Quality Assurance for the historical file.

Sam Faem OA 3 2-

IX-FE-101-2 October 1981 Page 6 of 6 PROCEDURE DEVIATION i

SITE' PROCECURE / REVISICN NO.

CEVIATION No.

PAGE DATE REGUESTED:

SECTION:

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SOUTHWEST RESEARCH INSTITUTE X-FE-101-2 NUCLEAR PROJECTS I

OPERATING PROCEDURE November 1982 Page 1 of 6 Title ONSITE NDE RECORDS CONTROL EFFECTIVITY AND APPROVAL Revision two of this procedure became effecove on 12/9/82

. This procedure consists of the pages and dunges listed below.

Page No Change Date Effective SA Accrovais Written 8y Date Technicot Review Date '

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Data Cognizant Dir at, '

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SOUTHWEST RESEARCH INSTITUTE x-rE-101-2 November 1982 NUCLEAR PROJECTS OPERATING PROCEDURE 1

i Page 2 of 6 ONSITE NDE RECORDS CONTROL 1.

PURPOSE This procedure describes the onsite control processes for nondestructive examination records (data) generated in the field during preservice (PSI) and inservice (ISI) examinations.

2.

SCOPE AND APPLICATION 2.1 This procedure describes the flow of data records used to document the results of nondestructive examinations performed.

Data records include original data sheets, summary sheets, resolution sheets, strip charts, magnetic tapes, video tapes, and other information as defined by the Inspection Engineer or Team Supervisor.

2.2 This procedure provides guidance to personnel of the NDE Field Services Section who are assigned the responsibility of preparing, reviewing, or otherwise using data records while in the field performing a preservice or inservice examination.

2.3 Functional steps are provided in this procedure to explain the flow of the records.

3.

RESPONSIBILITY (1)

The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be respon-sible for the preparation, review, approval, and control of this procedure.

(2)

The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan.

(3)

The Inspection Engineer shall be responsible for implementing the requirements of and ensuring compliance with this procedure.

(4)

The Manager of the Support and Administration Section, Quality Assurance Systems and Engineering Division, shall be responsible for storage of record.s generated in accordance with this procedure.

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Swfti Form QA 3 2

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SOUTHWEST RESEARCH INSTITUTE x-Fs-101-2 November 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 6 4.

PROCEDURE 4.1 Oriainal Data Sheets (1)

Original data sheets, are to be serialized either at SwRI or at the site.

(2)

Original data sheets shall be filled out at the examination location and during the examination time.

(3)

The filled-out original data sheets shall be returned to the team staging area (office, trailer, etc.) on a periodic basis (at meal time, at the end of the day, upon leaving controlled areas) during an ISI or a PSI, and an entry shall be made into a daily log indicating that the examinations have been performed.

(4)

The original data sheets shall then be placed into the To-Be-Reviewed File.

(5)

The review process is performed as follows:

(a)

The original data sheets shall be checked for completeness, accuracy, and consistency of the data.

(b)

If clarification or correction of any entry on the original data sheets is required, the original data sheets shall be returned to the examiner.

(c)

Af ter clarifications or corrections, if any, have been made and initialed by the examiner, the reviewer shall sign each original data sheet which does not contain indications requiring evaluation / resolution.

(6)

The original data sheets which have been reviewed and signed shall be moved to the To-Be-Summarized File. See Paragraph 4.1(9).

(7)

Original data sheets which contain indications requiring evaluation / resolution shall be placed in the To-Be-Resolved File.

SwAl Form QA 3 2

f SOUTHWEST RESEARCH INSTITUTE x-Ft-101-2 November 1982 g

NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 6 w

(a)

Original data sheets in the To-Be-Resolved File which document visual or surface examinations shall be handled as follows:

(1)

The Original data sheets shall be reviewed, signed by the reviewer, and used to generate a Customer Notification Form (CNF).

(The CNF shall be completed according to NQAP 13-1.)

I (2)

Copies of original data sheets shall be made and attached to the CNF.

(3)

A log shall be maintained of CNFs issued and their status.

(4)

The original data sheets are then placed in the To-Be-Summarized File. See Paragraph 4.l(9).

(b)

Original data sheets in the To-Be-Resolved File which document ultrasonic examinations shall be used to resolve the indications according to Paragraph 4.3 and shall then be processed as specified in Paragraphs 4.l(5) and 4.l(6).

(8)

When a computer is used to record results and generate summary sheets, data shall be fed into the computer.

The computer will generate the summary sheets at the completion of all required examinations of an examination area.

4 (9)

If the computer is not used to generate summary sheets, data placed in the To-Be-Summarized File shall be summarized according to Paragraph 4.2 and filed with the summary sheet in the original data volumes.

4.2 Summary Sheets (1)

Summary sheets, are to be serialized either at SwRI or at the site.

(2)

Summary sheets shall be completed for each examination area.

In certain cases (studs, nuts, etc.), one summary sheet may be used for more than one examination area.

Swm Form QA 3 2

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SOUTHWEST RESEARCH INSTITUTE x-rz-lol-2 November 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 6 (3)

Summary sheets shall be completed prior to the conclu-sion of site activities for each examination area for 1

which examination requirements have been completed.

(4)

Summary sheets shall be filed with the data in the original data volumes.

4.3 Resolution Sheets (1)

Resolution sheets, are to be serialized either at SwRI or at the site.

(2)

The Level II or Level III examiner shall take the steps necessary to resolve the ultrasonic indications and complete a resolution sheet describing the results of his analysis. Any additional documentation required to support the resolution shall be attached.

1 (3)

Original data sheets and resolution records with indica-tions requiring no further action shall be placed in the To-Be-Reviewed File and processed as specified in Para-graphs 4.1(5) and 4.1(6).

(4)

Data with indications requiring further action shall be handled in a manner established by the Director of the Department of Engineering Services.

4.4 Strip Charts, Magnetic Tapes. Video Tapes (1)

Strip charts, magnetic tapes, and video tapes being generated during mechanized ultrasonic examinations shall be identified with a sequence number and with the examination areas for which they contain data.

(2)

During the resolution of any indications, the strip charts and tapes may be used by the Level II or Level III examiner, as needed.

(3)

The strip charts and tapes are then prepared for transmittal to SwRI.

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5.

RECORDS 51 Prior to departing the site at the completion of a preservice or inservice examination, the original data package with the exception of strip charts, magnetic tapes, and video i

SwAl Form QA 3 2 i

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l SOUTHWEST RESEARCH INSTITUTE

<-rs-101-2 Rovember 1982 NUCLEAR PROJECTS OPERATING PROCEDURE 9 age 6 of 6 tapes shall be reproduced and a copy (ies) shall be transmitted to the appropriate site personnel. At no time will data be reproduced for this transmittal before the required examinations for a particular area are complete, the data has been reviewed, and the summary sheets have been completed.

5.2 After completion of site activities (or at other times deemed appropriate by the Inspection Engineer or Team Supervisor), the original data package shall be transmitted to SwRI in accordance with the latest revision of SwRI Nuclear Projects Operating Procedure XVII-AG-101.

SwRI Form QA 3-2

I SOUTHWEST RESEARCH INSTITUTE XIII-AG-101-2 NUCLEAR PROJECTS September 1982 OPERATING PROCEDURE Page 1 of 12 Title CONTROL OF NUCLEAR INSPECTION EQUIP!ENT AND MATERIALS EFFECTIVITY AND APPROVAL 2

10/4/82 Revision of this procedure became effective on

. This procedure consists of the pages and changes listed below.

Page No Change Date Effective 1-12 0

September 1982 SA Acorovals Written By Date Technical Review Oate

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Date Cognizant Direc'or _

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SOUTHWEST RESEARCH INSTITUTE nII-^c- 01-2 September 1982 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 12 CONTROL OF NUCLEAR INSPECTION EQUIPMENT AND MATERIALS 1.

PURPOSE 1.1 The purpose of this operating procedure is to provide control for the storage, inventory, issue, shipment, and return to stock of examination equipment and materials.

a 2.

SCOPE AND APPLICATION 1.1~

The scope of this procedure is the control of nuclear examination 3

equipment to ensure the integrity of equipment and materials used during the examination of nuclear power plant components. See NPOP VII-AG-102 for control of Search Units.

2.2 Controls are further required to ensure that maximum utilization is made of available equipment, i e., equipment is not " lost" in the

" Radiation Control facility, delayed or misplaced during transit from job site to maintenance shops, or allowed to remain out of circula-tion for long periods of time while being used for research and development projects. The flow chart illustrates the control and process of nuclear' inspection equipment (Attachment 1).

2.3 This procedure is applicable to, but not limited to, control of the following equipment and materials:

(1)

Ultrasonic Examination Materials and Equipment (2)

Plastic Wedges (3)

Penetrant 2xamination Materials u

(4)

Magnetic Particle Examination Materials and Equipment a

(5)

Eddy Current Examination Equipment and Standards f

(6)

Mechanized Examination Equipment r

(7)

Data Acquisition Systems f

2.4 The following hocuments form a portion of this procedure as applicable.

4.4.1 SwRI Nuclear Quality Assurance Program Manual (NQAPM).

h 2.4.2 SwRI Radiological Health and Safety Manual.

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i Swil Form QA 3-2

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SOUTHWEST RESEARCH INSTITUTE m I-Ac-lot-2 September 1982 NUCLEAR PROJECTS OPERATING PROCEDURE q

P 3 of 12 3.

RESPONSIBILITY i

t 3.1 The Vice President of the Quality Assurance Systems and Engineering l-Division shall designate one or more secure areas to be used for equipment and materials storage as control facilities.

1 3.2 Control facilities shall be operated by a Stock Clerk and an Equip-l ment Clerk. The Stock Clerk will be under the supervision of Inven-tory Control Traffic Manager who will be responsible for inventory storage and issue of examination materials. The Equipment Clerk, under the supervision of the Supervisor, Administration Control, will be responsible for inventory, storage, issue and retrieval of controlled equipment.

3.3 Responsible users, such as Team Supervisors, shall be responsible i

for compiling a list, using SwRI Form SS-17 Equipment Control /

j Shipping List (Attachment 2), of equipment and materials required 3

for each job or project. They shall be responsible for shipment of l

the equipment to the job site, security while at the job site, j

reshipment upon completion of the job, documentation of faulty l

equipment, and turn-in of equipment and unused utsterials.

i 3.4 The Division Health Physicist or his representative shall be respon-sible for accepting equipment and materials returned from an inser-vice examination, its decontamination, and returned to its proper storage facility.

3.5 The Assistant Manager, Technical Activities Group, or his alternate shall be responsible for providing minimum maintenance turnaround time and for providing current certifications as required for nuclear examination equipment.

4.

PROCEDURE 4.1 New Equipment 4.1.1 Newly purchased or fabricated critical equipment shall be inspected in accordance with SwRI Operating Procedure VII-AG-101 prior to being routed to the appropriate control facility.

r Swal Form QA 3-2

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v SOUTHWEST RESEARCH INSTITUTE m t-^c-

-2 September 1982 l

q NU, CLEAR PROJECTS OPERATING PROCEDURE Page 4 of 12 l 5 3

l 4.1.2 An identification number.(serial number) will be assigned to

?

'i noncapital; equipment which does not have a manufacturer's i

serial number.

4.1.3 Upon completion of proper identification, new equipment will g'

N be listed on the control facility inventory records.

s 4.1.4 Once new equipment is properly ide'utified and inventoried, s

it will be issued to the appropriate maintenance facility for an operational check and certification in accordance with NQAPM Procedure NQAP 10-1.

The maintenance facility will return the equipment, along with copies of certifi-cations generated,- to the control facility. The new equip-1 ment may then be issued for nuclear inspection work.

4.2 Equipment and Materials Issue

'4.2.1 When it is determined that equipment and/or materials are to be removed from the appropriate control facility, with the

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b

<k exception of equipment routed through the maintenance facil-ities (Paragraph 4.6.3), the Team Supervisor or Responsible User will compile a list of required equipment and materials needed using Form SS-17.

The responsible supervisor ~shall complete each blank at the top portion of the form with no exceptions.. On the second part of the, form, he will list quantity and nomenclature of coch ita of equipment or 7'~

materials required and indicate those which require certifications.

\\g 4.2.2 When the Team Supervisor or Responsible User has initiated Form SS-17, he may assign any. technician to draw and pack the equipment. The technician will present Form SS-17 to

OPERATING PROCEDURE June 1982 Page 1 of 7 Title DATA STORAGE AND RETRIEVAL EFFECT1VITY AND APPROVAL 1

2/10/81

. This procedure consists of the pages and Revision of this procedure became effective on changes listed below.

Page No Change Date Effective 6/22/82 1

1 2

0 2/10/81 3

1 6/22/82 4-7 0

2/10/81 s4 Accrovels Written By Date T nica Review Date h

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SOUTHWEST RESEARCH INSTITUTE January 1981 NUCLEAR PROJECTS OPER ATING PROCEDURE Page 2 of 7 DATA STORAGE AND RETRIEVAL

1.0 INTRODUCTION

1.1 Purpose This procedure establishes a system for the control and the storage of data for nuclear power plant components classified by ANSI N45.2.9, " Requirements for Collection, Storage, and Maintenance of Quality Assurance Records for Nuclear Power Plants." This operat-ing procedure satisfies the requirements of Appendix B to 10CFR50, Criterion KVII and the SwRI Nuclear Quality Assurance Program Manual.

12 Scope and Applica' tion 1.2.1 The scope of this procedure is limited to the documentation of nuclear power plant examinations performed by NDE Field Services, Quality Assurance Systems and Engineering Divi-sion, and to other documentation as designated by the Vice President, Quality Assurance Systems and Engineering Division.

1.2.2 This procedure applies to the Data Control Clerk, Team Supervisors, Inspection Engineers, and all other personnel who enter documents into and receive them from the Data Storage Facility.

1.2.3 Other divisions of the Institute may store quality assur-ance records for nuclear power plants in the Data Storage Facility. Once these records have been entered in the facility, they will be controlled according to this procedure.

13 Responsibility 1.3.1 The Manager of Support and Administrative Services within the Quality Assurance Systems and Engineering Division shall be responsible for the implementation and control of this procedure.

sam Fem OA 3 2

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SOUTHWEST RESEARCH INSTITUTE CMGE 1 XVII-AG-101-1 NUCLEAR PROJECTS OPERATING PROCEDURE June 1982 q

1 Page 3 of 7 l

1.3.2 The Data Control Clerk of Support and Administrative Ser-vices shall be responsible for controlling, filing, and i

maintaining documentation covered by this procedure in the i

Data Storage Facilities. The Data Clerk shall assume this responsibility when documents are received in accordance with Paragraphs 2.1, 2.2, and 2.3.

1.3.3 Team Supervisors, Inspection Engineers, and other personnel compiling documentation shall be responsible for ensuring completeness and accuracy of documentation being entered into the Data Storage Facility (see Section 2.0).

1.3.4 The Manager of Support and Administrative Services, or a representative, shall routinely review Section performance against the requirements of this procedure.

i 1.3.5 The Manager of Quality Assurance, or a designated repre-sentative, shall routinely audit performance against the l

requirements of this procedure and shall report the results I

of such audits to the Manager of Support and Administrative Services and the Vice President, Quality Assurance Systems and Engineering Division.

i 1.4

. Data Storsae Facility Description i

The Data Storage Facility for SwRI-retained quality assurance records is located in Building 139. The construction of the l

facility in Building 139 is concrete block with steel vault door.

The facility has a temperature control device to regulate tem-perature and humidity.

2.0 PROCEDURE l

2.1 Examination data and related material being sent to SwRI will be listed on Form SS-1, Records Transmittal and Receipt. Upon completion of the form and its arrival with the data at the Institute, they will be delivered to the Data Control Clerk.

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I SwRl Form QA 3 2

SOUTHWEST RESEARCH INSTITUTE xvii-AC-lol-1 January 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 7 2.2 Upon receipt of the data, the Data Control Clerk will use the trans-mittal form as a checklist to ensure that all material listed has been received. The Data Clerk will inventory the data by preparing a listing of Summary Sheet numbers or by entering the Summary Sheet number on a weld table. The Data Clerk will also ensure that each Examination Data Sheet listed on each Summary Sheet is in the Data Package.

In those cases where a Summary Sheet is not used or has not been prepared at the time of receipt of the data, the Data clerk will prepare a listing showing the serialized number of each data sheet received. The completed inventory will be filed in Section A of the file system.

In addition, the Data Control Clerk will ensure that all documentation to be stored contains the following:

(1)

Reactor Site Name (2)

Date of Record Entry (3)

Description of Material. Analog and video tapes and strip charts will identify the examination to which they relate and will be numbered. This information is entered by the Team Supervisor, the Inspection Engineer, or their designated alternates.

The Data Control Clerk will then enter the data into the Data Storage Facility.

2.3 PSI and ISI reports, other nuclear power plant examination reports, examination plans, etc., relating to a particular reactor will be furnished to the Data Control Clerk by the Report Coordinator.

2.4 Other records designated by the Vice President, Quality Assurance Systems and Engineering Division, as authorized for storage in the Data Storage Facility, will be furnished to the Data Control clerk.

l 2.5 Items being removed from the Data Storage Facility shall be signed out. Original field data will be returned to the Data Storage Facility at the end of each day.

If this data needs to be used after normal working hours, special arrcngements will be made with the Data Control Clerk. Other items may be signed out for the period required. The individual withdrawing data or other material l

shall be responsible for its safekeeping and return.

1 l

swMt Form QA 3 2 L-

" '-^ -' - ' '

SOUTHWEST RESEARCH INSTITUTE January 1981 NUCLEAR PROJECTS OPERATING PROCEDURE g

Page 5 of 7 2.6 The Data Storage Facility will be maintained in a neat and orderly manner. Records will be inside file cabinets or bookcases. Loose papers, drawings, etc., shall be placed in folders, binders, or envelopes for filing.

3.0 RECORDS 3.1 The Data Control Clerk will maintain an up-to-date list of records covered by this procedure and a list of their respective locations.

3.2 Data maintained in the Data Storage Facility will be retained for the periods indicated in Appendix A or according to written instructions furnished to the Data Control Clerk at the time the records are placed into the Data Storage Facility. The period of retention will in no circumstances be shorter than the time specified in the applicable contract.

3.3 Project Managers should review the records in the Data Storage Facility relating to closed projects to determine their ultimate dispositioning; i.e., return of records to client upon termination of contract, continuous storage in the Data Storage Facility, etc.

Decisions should be coordinated with the appropriate Director, and the Data Control Clerk should be notified in writing. The Data Control Clerk will comply with the written instructions.

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l swIt Form oA 3-2

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SOUTHWEST RESEARCH INSTITUTE January 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 7 APPENDIX A The following is a list of documentation and its retention periods as main-tained by Data Control in the Data Storage Facilities.

Record Type Retention Period (1)

PSI, ISI, and other examination reports, which Lifetime include:

Personnel certifications Search unit, material, and instrument ceetifications Zero reference location Weld identification isometric drawings Calibration standards Nondestructive testing procedures (2)

PSI, ISI, and other examination data, which Lifetime include:

Original data Video tapes Analog tapes Eddy current data Eddy current tapes Strip charts Equipment calibration sheets Record Type Retention Period (3)

PSI, ISI, and other examination plans Lifetime (4)

Photographs relating to nuclear power plants As determined by the Project Manager (5)

Logs, drawings, and summaries created by Lifetime field crews during an ISI or PSI (6)

General information that would be of value Lifetime in conducting future ISIS SwRlForm QA 3 2

SOUTHWEST RESEARCH INSTITUTE m -a-toi-1 January 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 7 (7)

Copies of procedures; personnel, material, and Destroy 6 months af ter instrument certifications; and other report issuance of Final data Report (8)

Other general information that will not provide Destroy after 2 years valuable information in conducting future ISIS I

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swII Form OA.3 2

APPENDIX B SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURE

APPENDIX B SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURE Table of Contents Procedure No./Rev.

Title l

SwRI-NDT-900-7/6 Visual Examination of Nuclear Reactors l

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SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-900-7 Re on l_

NUCLEAR PROJECTS o

,r 983 OPERATING PROCEURE Page 1 of 7 T!ae VISUAL EXAMINATION OF NUCLEAR REACTORS annenvrry Ano AmovAt.

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of M areassure memense erfenere on 11-18-83.

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SOUTHWEST RESEARCH INSTITUTE 8"*I;"" M

-7 November 1983 NUCLEAR PROJECTS OPERATING PROCEDURE g

Page 2 of 7 VISUAL EXAMINATION OF NUCLEAR REACTORS SwRI-NDT-900-7 1.

PURPOSE This procedure provides the technical information and detailed steps required to ensure the proper visual examination of nuclear power plants in accordance with the applicable ASME Boiler and Pressure Vessel Codes.

2.

SCOPE AND APPLICATION Direct and remote visual techniques shall be applied as specified for the examination of:

(1)

Nuclear power plant components (2)

Nuclear reactor internals (3)

Support members and structures for piping, valves, and pumps 3.

APPLICABLE DOCUMENTS (1)

ASME Boiler and Pressure Vessel Code,Section XI,1980 Edition with Addenda through Winter 1980, " Rules for Inservice Inspection of Nuclear Power Plant Components" (2)

SwRI Nuclear Quality Assurance Program Manual (NQAPM) l 31 Applicable Examination Record SwRI-NDTR Form No.17-28, revision dated 07-30-80 4.

RESPONSIBILITY (1)

The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible for the preparation, review, approval, and control of this procedure.

(2)

The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan.

Swfti Form QA 3 2

SOUTHWEST RESEARCH INSTITUTE

%^';" M

-7 November 1983 NUCLEAR PROJECTS OPERATING PROCEDURE q

Page 3 of 7 (3)

The examiner shall be responsible for implementing the requirements of this procedure.

(4)

Tito Manager of the Support and Administration Section, Quality Assurance Systems and Engineering Division shall be responsible for storage of records generated in accordance with this procedure.

5.

PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-2, " Procedure For Certifying Visual Examination Personnel."

5.2 Equipment The Visus 1 Examination Acceptability Test Card shall be made from Kodak Neutral Test Card No. R-27 or an equivalent, with an 18% neutral grey side having a 1/32-inch-wide black line across its center.

Commercially available equipment shall be used as required for the per-formance of examinations or operations by the techniques described in Para-graphs 6.1, 6.2, 6.3, and 6.4.

6.

EXAMINATION METHODS 6.1 VT-1 Examinations The examiner shall decernine the condition of the part, component, or surface with respect to cracks, wear, corrosion, erosion, or physical damage to the surface of the part or component.

6.1.1 Direct Visual l

Direct visual examination shall be performed by placing the eye within 24 inches of the surface to be examined and at an angle no less than 30 degrees with the surface to be examined. Mirrors may be used to improve the angle of vision, and aids such as magnifying lenses may be used.

In addition to the general lighting, illumination of the area to be examined shall be provided at right and oblique angles to expose cracks or evidence of corrosion or erosion.

Swat Form 0A 3 2 1

i 5"" " T- * -7 SOUTHWEST RESEARCH INSTITUTE Revision 6 November 1983 l

J NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 7 t

i:

Resolution shall be considered adequate when the combination of i

access, lighting, and angles of vision, either unaided or corrected, can resolve a 1/32-inch-wide black line on an 18% neutral grey card placed on the surface to be examined.

6.1.2 Remote Visual Technique f

Remote visual examination may be used where conditions exist that i

j do not permit direct visual examination. Remote visual examination may include l

visual aids such as telescopes, periscopes, borescopes, fiber optics, or video cameras and monitoring systems, with or without attachments for permanent recording. Remote techniques shall demonstrate the ability to provide a reso-i lutior. at least equivalent to that obtainable by direct visual examination.

Mirrors, movable lights, or rotating optics, or any combination thereof, may be employed to display cracks, surface scratches, or evidence of corrosion, ero-sion, misalignment, or movement. Scanning parameters, if required, for the remote visual examination shall be included in the applicable Swt1 Scan Plan.

Resolution shall be considered adequate when the combination of i

access, lighting, and angles of vision, either unaided or corrected, can

(

resolve a 1/32-inch-wide black line on an 18% neutral grey card placed on the surface to be examined or in a situation misilar to the area to be visually examined.

l 62 VT-2 Examinations The examiner shall locate evidence of leakage fros pressure -

retaining components, or abnormal leakage from components with or without leak-age collection systems as required during systes pressure or functional tests.

6.2.1 honinsulated conoonents The accessible external exposed surfaces of pressure retaining components shall be examined for evidence of leakage.

Examination of the surrounding area, including the floor or equipment located underneath the component, shall be required for components with inaccessible external surfaces.

6.2.2 Insulated Components Examinations may be conducted without the removal of insulation by examining the accessible exposed surfaces and joints of the insulation.

Vertical surfaces of insulation need to be examined only at the lowest eleva-tion where leakage may be detectable.

Horizontal surfaces of insulation shall

(

be examined at each insulation joint.

l 4

i Sw91 Form 0A 3 2

SwRI-ET-E-7 SOUTHWEST RESEARCH INSTITUTE Revision 6 November 1983 NUCLEAR PROJECTS OPERATING PROCEDURE j

q Page 5 of 7 Inaccessible piping and components shall require an examination for evidence of leakage on the surrounding floor areas, equipment surfaces located underneath the component, or other areas where leakage may be channeled.

Discoloration or residue on surfaces examined shall be given particular attention to detect possible boric acid accumulations from borated reactor coolant leakage.

6.3 VT-3 Examinations The examiner shall determine the general mechanical and structural conditions of components and their supports, such as the presence of loose parts, debris or abnormal corrosion products, wear, cracks, erosion, corrosion, and the loss of integrity at bolted or welded connections.

6 3.1 Vessel Internals The areas to be examined shall include major load-bearing elements of the reactor internals which are relied upon to retain the core structure in position; the lateral, vertical, and torsional restraints within the reactor vessel; the locking and bolting devices whose failure could adversely affect the structural integrity of the internals; surfaces that are known to be or may become contact surfaces during operation; critical locations on reactor inter-nal components as identified from the vibration analyses; and the interior of the reactor vessel for evidence of loose parts or foreign material.

6.4 VT-4 Examinations This examination shall be performed to determine conditions relat-ing to the operability of components or devices such as mechanical and hydrau-lic snubbers, component supports, pumps, valves, spring-loaded hangers and l

constant supports.

Functional adequacy, verification of settings, or freedom of action shall be determined.

The support settings of constant and variable spring-type hengers, snubbers, and shock absorbers shall be recorded in the REMARKS section of the SwRI Visual Examination Record.

The scale reading of hangers having calibrated load indicators shall be recorded in the REMARKS section of the SwRI Visual Examination Record.

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s.nl Form cA 3 2 l

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SOUTHWEST RESEARCH INSTITUTE S",*I$j-7 g

November 1983 s

NUCLEAR PROJECTS OPERATING PROCEDURE q

Page 6 of 7 4

Hydraulic snubbers shall be examined for signs of fluid leakage at shaft seals, joints, and couplings. Shaft extensions shall be examined for scratches, cuts, and gouges.

Hanger springs shall be examined for integrity to ensure that springs have not sheared.

Pipe clamps and U-bolts shall be examined to ensure that they are securely attached to the pipe.

7.

Examination 7.1 Surface Cleanina Visual examinations which require clean surfaces or decontamina-tion for valid interpretation of results shall be preceded by appropriate cleaning processes.

Examinations may be required where the surface is painted or has other types of coatings. This shall be permitted if it is determined that such coatings do not interfere with valid interpretation of results.

7.2 Examination Areas Components, parts, and areas to be examined shall be as specified in the applicable SwRI Examinatios. N an.

Remote visual examinations utilizing mechanised scanning devices shall be as specified in the applicable Scan Plan.

Scanning parameters, if required, for the remote visual examination, shall be included in the applicable SwRI Scan Plan.

8.

RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined I

in the applicable revision of SwRI Nuclear Projects Operating Procedure i

IX-FE-116 for direct visual examinations. Indications detected in remote visual examinations shall be recorded in accordance with the customer's specifications, remote equipment manufacturer's specifications, or the SwRI j

j Scan Plan, if applicable.

Visual abnormalities shall be recorded on the SwRI Visual Examination Record and reported to the customer.

l l

l SwMl Form QA 3 2

I SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-900-7 Revision 6 November 1983 NUCLEAR PROJECTS OPERATING PROCEDURE q

Page 7 of 7 9.

EVALUATION Evaluation of reportable indications shall be the responsibility of the customer, or the customer's representative, and shall be conducted in accor-dance with Article IWA-3000,Section XI, of the applicable ASME Boiler and Pressure Vessel Code.

10.

RECORDS The customer shall receive copies of documents generated in accordance with this procedure in the examination report.

Documents generated in accordance with this procedure shall form a part of the examination report which shall be stored by the Manager of the Support and Administration Section, Quality Assurance Systems and Engineering Division, in the Data Storage Facility for the period specified by the contractual agreement with the customer.

$dl Fum OA 3-2

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l APPENDIX C CERTIFICATES OF PERSONNEL QUALIFICATIONS l

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l CERTIFICATES OF PET SONNEL QUALIFICATIONS Table of Content.s.

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SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION The Director of the Department of Engineenne Services. Queitey Assurence Systeme and Enganoonng DMeson. certifice that II VT-1, VT-2, Steve Magaro le quened es w h vhued Teesirig (VT). ceeegorise VT-3, VT-4 w

,,,,,,,,,n in.,oguvements of SwAI Nucaser Quality Assurance Procedure 112. Mewieson 2.

cerenoemen umiseeene:

• Certification valid oniv while employed by SwRI sY

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08/24/84 // //h,f

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Esperosen Does.

1. NN/2 purester, popertment et ;.;1- - -

Date:

signed:

t EDUCATlON. TR AINING ANO EXPERIENCE HISTORY EDUCATION:

NAME YEARS DEGREE TRAINING (thie method end level):

Robert E. Lee (Tx) 3 CRAD Dese Compissed:

06/24/81 High seheel 4 gi I

St. Philip's College 3

No 12 SwRI g,,,.

Maser risid of study Welding Does Empeeved by awal:

01/22/79 p,,,,,,, uog,,,,,,,,, ii,,,,,,,, ousencemen t:

The bieMdualhee been crediend wie 7 mones of espersoneein mis esemenselon method on the dess of cerW6eetion, some of the espertones may have None been eserved simWeeneeweiy with omer NDE methees (et least 28% was in this meshed).

VISUAL ACUlTY ANO COLOR PERCEPTION The ineleviduelle espekte of reading Jaeger Nurnber l lettere et 12 inches, and is cemette of reading Sneden Number 30 lettere et a diesence of 20 feet, in et least one eye f uswig corrective lensee if spes#And boiowl, and can dissingush and different6ees centreet between coloro used in this enethod.

Cerr.

Corr.

Does Reg.

Ver6Med by Date Reg.

Venned by 08/06/81 No lleidi Cutierrez 'f[-

07/82/82 No lieidi Cutierrez 4/af 07/05/83__

No lleidi Cutierrez

' DST REC 2NT EX AMIN ATION ORACES CERTIFICATION HISTORVs THIS LEVEL Scorse Weight Date 08/24/81 cene,el:

97.50

.33-1/3 inical ce,,,neet,en:

spe ene:

96.00

.33-1/3 noon,nes,en:

{

88.25

.33-1/3 Pruscal:

I 93.92 1.00 c,.

Mecentncation:

o.

06/23/81; 06/24/81 J.C. Codwin 4 7M 6(7. k Respenobie tevol m.

REMARKS s.airo,m oA.e o C-1

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SOtJTHWEST RESEARCH INSTITUTE l

,q NONDESTRUCTIVE EXAMINATION i*

STATEMENT OF CERTIFICAT10N l

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The VIce Pneedent. Quanty Assurance Systems and Engir eenng Olvimon, crtmos mat Robert ?. Shirikus is cuev,ed as Loves ill in visuoi Tesong tyn, categones Vt-l, VT-2. VT-3, VT-4 in accordance with the requwemen of SwRl Nucteer Quanty Assurarte Procedure 112. Rev;enon 2.

m oi,,,,,,, ion,. s -

Certification valid only while en: ployed by SwRI Expiration Dete.

09/02/84 I

s Signed:

Date:

Mecent. Cues seurance Systems and Lir y Orvimon

//

EDUCA7 TON ANO EXPERIENCE HISTORY EDUCATICN:

NAME YEARS CEGREE Previous NCE exponence (if used for cushficationi:

Marcellus H.S. (Mich) 4 GRAD g9 3,3,,,

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,,,,,ny 7,

1 Michigan State Univ.

4 B.S.

Republic Steel Corp.

1948 1952 m

Goodyear Aircraft Corp.1952 1953 K

Craft Metal Fabrictg.Co.1953 1955 Maior Fie6d of Study Meta 11urefcal Engineering Gqodvear Aerospace Corp.1958 1968

Jestinchouse Electric 7968 1970 4te Emosoyed tw SwRi:

-01/06/70 The individua# has been credites w er. et ionst 396 mone,,,,,,,n.n y

vi t*ne examinanon memod m sne cata of cornficanon. Some of the empenence may have been scerueo smultaneousy. m other NOE metnods (at least 25% wee w trus.cnnoon.

7 y

VISUAL ACUITY ANO CCLCR.*ERCEPTION Du Mvidual is capab6e of reading Jaeger Numoer 1 lettra et 12 inches, and is capac6s of ree #,g Soesten Number 30 letters at a distence of 20 feet. in at least one eye (uemg corror.tve ioness if erocrhed bescwl, and can distingush and drfferenants cont rst between colors used in mis memod.

Corr.

Ccer.

r Date Rec.

Venfied by Date Req.

VenfW by 10/03/80

.Yes Helidi Gutierrez.dG 05/23/83 Yes HeidiGutierrer./fa 09/23/81 Yes Heidi Cutierrez Af%

f 05/18/82 Yes-Heidi Gutierrez 1/g MOST RECENT EXAMINAT)CN GR ACES '

CERTIFICATION HISTORY: THIS LE'/EL i

Scorer Weignt

'Jate cenerec 88.05 O.5 inman Cernficanon:

01/02/74 speciec; 92.21

0.5 Recruficanon

01/02/77

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N/A N/A Recernficanon.

01/02/80 practican Comoo.t.:

90.14 1.,0 a,,,,,,,ie,non.

09/02/81 Recernficanon:

05/15/8OM. //.s ca e:

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REMARKS

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S*RI Form CA.a3 0 C-2

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SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION g

STATEMENT OF CERTIFICATION The Director of the Departrnent of Engineenng Services. Queaty Assurance Systems and Engmeenne Divieson. cerofies that II James Wardwell is ousained as w in viouse Testing (vn. categories vT-1. VT-2_

VT-3. VT-4

% accordance with the requiremonte of SwRl Nucteer Quelity Assurance Procedure 112. Revenson 2.

Certification valid only while employed by SwRI CertReseon umitecone.

Al Espeedon Dete:

08/24/84

[ N/Mr....

NNb Date:

Signed:

parector, c:;m. c.t of Eng=*enne syes ~ v i EDUCATION. TRAINING AND EXPERIENCE HISTORY EDUCATION:

NAME YEARS DEGREE TRAINING (thie method end leven:

High School Thomas Jefferson (Tx) 4 GRAD Dete completed:

06/24/81 Addisones Hours:

17 Location: SwRI Maior Field of Study 09/05/79 Dete Employed by SwA1:

p,s,,ou NDE suponence (if used for queirncedoni:

The indMdual hee been credited with 11 months of experience in this enemmetion method on the date of certracation. Some of the emperience may have been accrued NC..

'; with other NDE methods (et least 25 % wee in this methodl.

VISUAL ACUITY AND COLOR PERCEPTION The indMdualle capable of reading Jonger Number 1 lettere et 12 inches. end is capetie of reedmg Snesen Numbef 10 lettere et e distence of 20 foot. In at least one eye (usmg correcthre leness if speedied below). and con M # end differentiate contreet l' anan colore used in this method corr.

corr.

Deve Req.

Vermed by Date Re.

Venned by 04/30/81 Yes

• Heidi Gutierrez ((G 01/11/84 No(nenri Yes(far) Heidi Gutierrezr 03/12/82 No(near) Yes(far)Heidi Gutier'rer/d 01/17/83 No(near) Yes(far)Heidi Gutierrez MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL Scoree Weight Date cenerei.

77.50

.33-1/3 inines c.,,gic,, ion.

08/24/81 Speedic.

70.00

.33-1/3 Recortincadon-Prececal.

94.00

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com,oene 80.50 1.00 nec,,,gie. con.

Recortification Dete:

06/23/81: 06/24/81 n,c.,,,ne,3,n.

J.G. Godwin h

,MN Respon.Mc Levoi m:

REMARKS

• For far vision only Sw AI Form OA-424 C-3

I 1

APPENDIX D NUCLEAR REGULATORY COMMISSION INSPECTION AND ENFORCEMENT BULLETIN NO. 80-13 I

SSINS No.:

6820 Accession No.:

UNITED STATES 8002280661 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 May 12,1980 IE Bulletin No. 80-13 CRACKING IN CORE SPRAY SPARGERS Description of Circumstances:

Instances of cracking in core spray spargers have occurred at two BWR facilities.

This trend indicates a need for more intensive inspection of these components during subsequent refueling outages.

Oyster Creek Nuclear Generating Station Jersey Central Power anti Light Company notified the NRC on October 18, 1978, that a crack had been found in Core Spray Sparger System II during remote visual inservice inspection at their Oyster Creek Nuclear Generating Station.

The crack was located at 208* azimuth and extended at least 180" circumferen-tially around the sparger.

An evaluation of the event by the licensee postu-lated that deformation of the sparger had occurred during fabrication and installation which led to cracking by Intergranular Stress Corrosion Cracking (IGSCC) during service in the BWR environment.

A temporary repair was effected by installing a clamp assembly over the crack.

The licensee's analysis indicated that the crack had relieved the stresses present and therefore precluded further cracking.

The NRC safety evaluation permitted operation until the next refueling outage and required inspection of the sparger at that time.

The NRC was informed by the Jersey Central Power and Light Company on January 16, 1980 that further cracking was discovered in the core spray spargers during an inservice inspection conducted in conjunction with the refueling outage.

A total of twenty eight cracks 0.001 to 0.002 inches in width and of varying lengths were identified in both core spray spargers.

The licensee stated that they believed the majority of additional cracks were present earlier and not discovered during the 1978 inspection due to inspection equipment limitations.

Near term repair consisted of the application of nine additional clamp assemblies in areas of the spargers where cracks were visually observed on the accessible portion of the sparger and UT indications were present in the inaccessible portion of the sparger and in the junction box region.

The licensee analyzed the flow characteristics of the spargers and determined that adequate flow distribution would be main,tair.ed if thru wall cracking.005 inches wide and 180* in length were present.

The licensee stated that the installation of the clamps would assure the sparger would maintain its physical integrity and remain in place.

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IE Bu11 tin No. 80- 13 May 12, 1980 Page 2 of 3 The repair measures proposed were determined by the NRC to be adequate until the following refueling outage.

The NRC evaluation stated that actions should be taken to develop and install an improved replacement system at the following refueling outage.

Pilgrim Nuclear Power Station On January 31, 1980 the Boston Edison Company (BEco) informed the NRC that five indications in the upper core spray sparger and two indications on the lower core spray sparger at the Pilgrim Nuclear Power Station were identified during remote visual inservice inspections.

The indications were confirmed as cracks after hydrolasing and brush cleaning.

The licensees evaluation indicated that the sparger will retain structural integrity throughout the next cycle, although core spray flow distribution may be affected due to through-wall cracks.

However, core spray flow delivery to the shroud interior would not be expected to decrease.

A loose parts analysis was presented which addressed (1) corrosion, (2) flow blockage, and (3) control rod interference.

To' support power operation in Cycle 5 with the core spray sparger in its present condition, BEco.has reanalyzed ECCS taking credit only for coie spray reflood, taking no credit for core spray heat transfer.

The submission by BECo is currently under review by the staff.

The analysis is expected to cover a full spectrum of core spray failures.

It is expected that the limiting condition will be the failure of recirculation suction line.

A MAPLHGR limit reduction will likely be imposed during Cycle 5 to compensate for the assump-tion of no core spray heat transfer.

Based on results from other sparger inspections and previous pipe cracking experience, cold work and sensitization during fabrication and installation stresses are considered to be the major factors in causing the observed cracks at the Pilgrim Station.

The cracks are hypothesized to be initiated ano propagated by intergranular stress corrosion (IGSCC).

A meeting was held with representatives.from GE in Bethesda, Maryland on March 13, 1980 to discuss core spray sp~arger cracking at BWRs. At the meeting GE provided the following information:

1.

In February 1979, GE issued to BWR licensees Service Information Letter (SIL) No. 289 that recommended inspection of the core spray spargers for visual indications of cracking.

To date, 19 of 21 plants inspected have no observed cracking.

Cracks have been found at 2 facilities (Pilgrim and Oyster Creek).

2.

The key contributors to IGSCC vary from plant-to plant, although stresses from cold work and sensitization during fabrication and installation are considered prime factors leading to IGSCC at Pilgrim and Oyster Creek.

Because the cause of cracking is not yet confirmed by metallurgical analysis, GE is developing tooling to extract sparger samples to verify the postulated cracking mechanism.

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IE Bulletin No. 80-13 May 12, 1980 Page 3 of 3 3.

GE is evaluating methods of improving'the sparger inspection techniques, and is considering a modification to the SIL, if warranted.

The staff agreed that improved inspection techniques should be developed and metallurgical examinations should be performed to determine the mode of failure.

The staff asked GE to keep them informed of progress in these areas.

Actions to be Taken by Licensees:

For all boiling water power reactor facilities with an operating license:

1.

At the next scheduled and each following refueling outage until further notice, perform a visual inspection of the Core Spray Spargers and the segment of piping between the inlet nozzle and the vessel shroud.

Remote underwater TV examinations are acceptable if adequate resolution can be demonstrated.

The viewing in situ of 0.001 in. diameter fine wires is considered as an acceptable means of demonstrating suitable resolution of the TV examinations.

Such techniques as the use of oblique lighting, and the ability to light from each side independently are considered useful in enhancing the image of cracks to facilitate detection.

2.

In the event cracks are identified during examination of the core spray sparger system, the location and extent of the indications shall be recorded and reported to the NRC.

Supplementary examinations using volumetric methods may be performed to aid in characterizing the extent of cracking in nonvisible locations.

An evaluation shall be submitted to NRR for review and approval prior to return to operation.

3.

Any cracking identified in the core spray cooling system shall be reported to the Director of the appropriate NRC Regional Office within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of identification.

4.

A written report of the results of the examinations including any corrective measures taken shall be submitted within 30 days of the comple-tian of the examination to the Director of the NRC Regional Office with a copy to the NRC Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Washington, D. C.

20555.

Approved by GAO, B180225 (R0072); clearance expires 7-31-80.

Approval was given under a blanket clearance specifically for identified generic problems.

r APPENDIX E RELOOK RESULTS - 2/24/84

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APPENDIX E RELOOK RESULTS - 2/24/84 Tape Indication Count Number Discussion 000 Core spray piping (345*)-to-elbow.

Reexamination and enhancement resolved the HAZ indication to be insignificant.

153 Approximately 10* azimuth midplane between nozzles 31 and 32.

Insignificant.

176 "A" junction box-to pipe weld on 0* side.

Five indications were enhanced on-line and shown to be insignificant.

245 53.5" support bracket, 0* side, resolved to be insignificant.

" A" sparger.

273 53.5* support bracket, 90* side, resolved as insig-nificant.

"A" sparger.

298 "B" sparger (345*), 0* side, weld and nozzle B25.

Indications observed during previous examinations.

There were no observable changes.

391 "B"

junction box, 270* side, no significant indications.

480 "D" sparger between 233.5 and 265.5" support brackets.

Heavy longitudinal indications were resolved as rub marks (see tape count 800).

576 "D" junction box,195 *, on the 270* side. Very fine indication at bottom of sparger piping does not appear to have changed from 10/81 examination.

On the 180* side, the indications on the junction box are not significant as they have been observed during the previous 2 examinations and exhibit no change.

704 "C" junction box, no significant indications.

h "C" sparger between 233.5* and 265.5* support 732 brackets.

Indication is iasignificant.

E-1 i

l APPENDIX E RELOOK RESULTS - 2/24/84 (Cont'd)

Tape Indication Count Number Discussion h

"C" junction box (165*) from 180* side.

Indica-746 tion at weld toe in HA2. has not changed and is considered to be insignificant.

h "D" sparger between 233.5* and 265.5* support 800 brackets shows the heavy rub mark indication to be insignificant when viewed and lighted from below.

Also see 8 above.

NOTE:

Iower sparger (B&D) indications were difficult to resolve due to many blade guides stored adjacent to the core shroud. Many blade guides were raised an estimated 12 to 24 inches above normal making some areas

-inaccessible for relook.

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