ML20054L454
| ML20054L454 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/31/1981 |
| From: | Alan Anderson SOUTHWEST RESEARCH INSTITUTE |
| To: | |
| Shared Package | |
| ML20054L447 | List: |
| References | |
| 17-6676, NUDOCS 8207080137 | |
| Download: ML20054L454 (90) | |
Text
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SOUTHWEST RESEARCH INSTITUTE Post Office Drawer 28510 6220 Culebra Road San Antonio, Texas 78284 1981 REMOTE VISUAL EXAMINATION OF THE CORE SPRAY SPARGER SYSTEM OF PILGRIM NUCLEAR POWER STATION, UNIT 1 FINAL REPORT SwRI Project 17-6676 Prepared for O Boston Edison Company Pilgrim Nuclear Power Station RFD 1, Rocky Hill Road Plymouth, Massachusetts 02360 December 1981 Prepared by Approv by
$N (f.
/ Wayne T.ffach Director
- Department of Engineering Services Quality Assurance Systems and Engineering Division DR OC O 00 3 O PDR
ABSTRACT A remote Visual (VT) examination of the core spray sparger system of the Reactor Pressure Vessel (RPV) of Boston Edison Company's (BECo) Pilgrim Nuclear Power Station, Unit 1, was performed during the October 1981 refueling outage.
The first remote VT examination during the initial 10 year inspection period was performed in Jar'tary 1980. The January 1980 examination indicated four areas of concern which were reported to BECo on Customer Notification Form (CNF) No. 000002 dated February 2, 1980. All areas which revealed indications were reexamined in October 1981 using improved equipment, lighting, and enhance-ment e c'.mique s .
All but two of the previously reported indications were resolved as being insig-nificant (grinding marks, or could not be reestablished). The remaining two indications were determined not to have changed since the 1980 examination and have stabilized with regard to crack propagation. Further area degradation is not anticipated.
No other recordable indications were observed.
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TABLE OF CONTENTS Zage, LIST OF ABBREVIATIONS . . . .. ... .... . . . . . . . . . . . . . vii I. INTRODUCTION . ... ...... . . . . . . . . . . . . . . . . . 1 A. Examination Areas .. .... . . . . . . . . . . . . . . . . 1 B. 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 E. Summary Table . . .. ....... . . . . . . . . . . . . . 4 APPENDICES A. Southwest Research Institute Nuclear Projects Operating Procedures B. Southwest Research Institute Nondestructive Testing Procedure C. Certificates of Personnel Qualifications D. Field Memorandum to BECo as Amended After Reviewing Computer-Enhanced Photographs E. Reference Sheets Relating 1980 to 1981 FIELD DATA Core Spray Nozzles Core Spray Piping and Header Core Spray Sparger Piping v
LIST OF ABBREVIATIONS ASME - American Society of Mechanical Engineers BECo - Boston Edison Company CNF -
Customer Notification Form ISI -
Inservice Examination NDT - Nondestructive Testing NRC - Nuclear Regulatory Commission QA -
Quality Assurance RPV -
Reactor Pressure Vessel SwRI -
Southwest Research Institute VT -
Visual Examination O
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I. INTRODUCTION During the October 1981 refueling outage, Southwest Research Institute (SwRI) personnel 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 examination and was per-formed to meet the intent of the Nuclear Regulatory Commission Inspection and Enforcement Bulletin No. 80-13.
A. Examination Areas 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," 1974 Edition, with Addenda through Summer 1975. In addition, the examination addressed the requirements of the Inspection and Enforcement Bulletin 80-13 for visual resolution of a 0.001-inch diameter wire placed in the examination area.
SwRI Project Plan for the 1981 Inservice Remote Visual Examination of Pilgrim Nuclear Power Station, Unit 1.
As a continuing observation of the indications detected during the January 1980 outage, the following components and areas were examined using the O remote VT testing techniques.
Reactor Pressure Vessel Core Spray Nozzles Core 3 pray Piping and Header Core Spray Sparger Piping B. Summary of Examination Results The remote VT examinations were conducted in accordance with SwRI Nonde-structive Testing (NDT) procedure 900-2, Rev. 7, Deviations 1 & 2, 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.
The remote VT examinations revealed numerous insignificant indications.
The linear indicacions reported on CNF 000002 as a result of the 1980 examina-tion were closely scrutinized and computer enhanced for better resolution. All but two of the previously reported indications were resolved as insignificant; i.e., grinding marks or shadows. 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 1980 examinations, several examination areas were limited because of structural
(] interference.
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l II. DETAILS OF THE INSERVICE EXAMINATION This section of the report provides a discussion of the equipment used and radiation exposure encountered during the inservice inspection (ISI), an expla-nation of field data records and a summary of the nondestructive examinations performed.
l A. Equipment i
A remote video system provided by CTS Consulting Personnel Services Inc.,
was used for the VT examinations. Certain portions of the video tape recorded \
data was computer enhanced to improve resolution. The video enhancement equipment was provided by APTEC Imaging, Inc.
B. Radiation Exposure
> Radiation exposure encountered during the examinations was of fundamental a i concern to all SwRI personnel involved during the daily examination activities. *
- SwRI personnel took the necessary precautions in order to minimize overall expo-sure and consequently received the minimum dosage practicable while performing the examinations. The radiation level on the refueling crane, where the exami-nation personnel were primarily located, was approximately 15 mrem per hour. '
1 C. Explanation of Field Data Records i
The results of the examinations performed by SwRI personnel were recorded
l j on standard SwRI forms. These completed documents constitute a portion of the i ISI report. The original records are retained in the SwRI Data Storage Facil-ity, and copies are provided herein for completeness.
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The Visual Examination Record Sheets for each examination area are assen-bled 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 examinations. Also, the material used in the examinations are also identified on the sheets.
D. Summary of Nondestructive Examinations The following sections of this report are presented for explanation of the Summary of Nondestructive Examinations Table (Summary Table). The Summary Table provides information and results for the nondestructive examinations per-formed during the October 1981 refueling outage.
- 1. ASME Section XI Item No. and Category The ASME Section XI Item No. and Category are listed in the first and second columns respectively.
! 2. Examination Area Identification Column J
In the column entitled " Examination Area Identification," each compo-
! nent examined (nozzle, cladding, patch, etc.) is identified by the component j description. The azimuth location for some of the components is also provided.
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- , , . - , - - - ,- , - - , , - - - - y , , . , , ,w,-g--v ,,-,n.,- - - ..-----v.,,,, , - - ,yg .---~,,---we-4-----,--- ,-,--w-------,---,e-- m.-
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- 3. Examination 'Methoo Column ,
The NDT exakinations required by Code, which for this scope of work is remete visual./,VT), are identified in this column.
- 4. SwAI Procedure Identification Column The fifth column of the table lists the SwRI NDT Procedure used for the examinations. The remote VT examinations were performed in accordance with i SwRI Procedure NDT-900-2, Rev. 7, Deviations l'& 2.
- 5. Summary She_er. Col _umn ,i
- s. .
The column entitled " Summary Sheet No." returences the summary sheet provided for each examination area. The summar? ' sheets are included in the field data section of this report. l'a addition to s'ummarizing the results of <
the examinations, the ; summary sheets litt the record sheet numbers, the SwRI I
examinar, dates of the examinations and resolution-sheet numbers.
- 6. Indications Columns The four columns under the general heading of " Indications" are "No Recordable," " Insignificant," " Geometric" and "Other." These columns wera used as required, and their general description is provided below.
The results for the remote VT examinations are indicated by an "X" in the appropriate column to be either "No Recordable," " Insignificant" or "Other." The term " Insignificant" is used for those indications that the exam-iner observed but determined were of a nature that did not require reporting to the customer. "Other" is used when indications are observed that are of a nature that should be reported to the customer.
- 7. Remarks Column The
- Remarks" column is used to provide additional information perti-nent to the examination results:
When complete coverage of the examination was not possible, the
" Remarks" column was used to indicate the limitations.
For examination results reported in the "Other" column, a brief description is given in the " Remarks" column.
When reference is made in the " Remarks" column to a CNF used in the reporting of indications.
E. Summary Table The Summary Table is located on page 5 of this report.
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l i FILGklM NUC1.EAk IWE4L STATION, UNIT 1 i 1981 INSERVICE EptliE VISUAL EXAMINAT!uNS i
.__ REACTOR PRESSURE VESSEL ASML ASME Sv.Hg witp gNO gCA { gONS SEC 71 SE C. Al PHOCEDuMt EKAM SUM HEMAHKS AHEAIDENIM4M W MEI M Ilk M NO CAIGY NG/HEV. SetE E I NO. NO *ECOftDA8L E INSIGNIF LCANI GEOME IH6C OTH&H CORE SPEAY I.3NES N0ZZl.ES AND ATTACMMENTS Bl.16 3-N-2 Core Spray Sparger VT 900-2/7 301000 1 Remastaattom of the support areas Numale 408 6 415 Dev. 162 revealed that the 1980 indicatione were the result of grinding to remove weld veJercut. Resolution
. determined by camera angle previously unavailable. Emanined
! only half of weld due to proximity of core shroud wa!!.
Bl.16 3-N-2 Core Spray Sparger VT 900-2/7 301001 I Renamination of the 1980 llaear Junction Bom-to-Pipe Dev. 162 todication revealed no apparent
- 345* to Noaste 25B change and that crack had stabi-lized. Emanteed only half of weld due to proalmits of core shroud
, wall.
Bl.16 B-N-2 Core Spray Sparger WT 900-2/7 301002 X Reementaation of the 1980 indication a u 165* liaaJer Dev. 162 revealed no current ladication.
l Suspect that the 1980 ladication was a shadow. Improved !!ghting enabled better observation. Emmatoed only half of welJ due to proximity of core shroud wa!!.
Bl.16 B-N-2 Core Spray Sparger VT 900-2/7 M1003 I Reemastsattoo of the 1980 toJication
'15* lleaJer Dev. R&2 confirmed by meses computer enhance-
"A" Sparger meat techniques. Ileat-affacted zone crack to the lower quadrant.
Essained only half of weld due to premietty of core shrouJ wall.
1 l Bl.16 B-N-2 Core Spray Sparger VT 900-2/7 301004 X Reementaation of the 1980 indication
- "A* Sparger 2 70* De v. 162 resolved the ladication as laatset!! cant.
j Bl.16 B-N-2 Cure Spray Sparger VT 900-2/7 301005 K Reemaatmattoo of the 1980 indication J' "C" Sparger 195* De v. 162 revealed no current ladication.
Area was wire brushed duties reemaa-saation and no ladication could be
- found.
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APPENDIX A SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDLTES O
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APPENDIX A SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE 9 Table of Contents Procedure No./Rev. Title IX-FE-101-1 Deviations to Nuclear Field Services Section CHANGE 1 Operating Procedures X-FE-101-1 Onsite NDE Records Control XIII-AG-101-1 Control of Nuclear Inspection Equipment and CHANGE 1 Materials XVII-AG-101-1 Data Storage and Retrieval O
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SOUTHWEST RESEARCH INSTITUTE Ix-PE-101-1 September 1976
- h. NUCLEAR PROJECTS OPERATING PROCEDURE R'
l g' Page 1 of S U k s e* DEVIATIONS TO NUCLEAR FIELD SERVICES SECTION o b OPERATING PROCEDURES 3 1: 1.0 PURPOSE 5%
$ '[ 1.1 The purpose of this operating procedure is to estab1ish guide-
! h lines and controls for deviations to Nuclear Field Services
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Section operating procedures.
SCOPE AND APPLICATION
.<?' . 0 2.1 This procedure applies to Nuclear Projects Operating Procedures
[y used by the Nuclear Field Services Section.
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Qg 2.2 Deviations written in accordance with this procedure shall be applict.ble only to the specified plant and examination area
( ]y Ss it described in the Request for Procedure Deviation Fom FE-4-3
% (sample attached).
i b d 2.3 Deviations written in accordance 'with this procedure do not con-stitute permanent changes or revisions to the applicable pro 4 p% cedures.
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% 2.4 This procedure meets the requirements of SwRI Nuclear Quality s Assurance Program Manual (NQAPM).
J 3.0 RESPONSIBILITY 3 /O W,p i '
3.1 The Director of the Depart =ent of Engineering Services, or his designated alternate within the Quality Assurance Systems j y% and Engineering Division, shall be responsible for the initia-tion of this procedure.
4 3 # 3.2 Qualification of deviations to operating procedures shall be a t the responsibility of the Director of the Department of Engi-2 neering Services, or his designated alternate.
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- SwAl Form GA-3-1
O SOUTHWEST RESEARCH INSTITUTE 1x-rE-iol-1 September 1976 k NUCLEAR PROJECTS (Rk?g tl -
OPERATING PROCEDURE Page 2 of S U k 3.3 The Manager of the Section, Team Leader, or other cognizant
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persons using the procedure shall be responsible for initiating the request for a deviation to the operating procedure.
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. 3.4 The Department Director, or his designated alternate, shall be 3'
! S1 responsible for approval of operating procedure deviations.
9 N 3.5 The Manager of Quality Assurance, or his designated alternate,
) la shall be responsible for reviewing and approving proposed (h
a *t deviations to operating procedures against the requirements of this procedure.
, M
]y'4.0 PROCEDURE
$ 4.1 The Manager of the Section, Team Leader, or other cognizant v persons who require a deviation to a Nuclear Field Services g 9%
D Section operating procedure shall be responsible for initiating a Request for Procedure Deviation Form FE-4-3. Deviations may j% be required due to changing technology, applicable code changes N or interpretations, plant or component design, customer require-ments, or special cases.
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$9% If the request for procedure deviation is initiated by a telephone call from the field, and the requestor is not avail-y able to sign the request, his name shall be typed in the j Y " Requested By" block.
3 4.2 The Manager of the Nuclear Field Services Section, or his designated alternate, shall assign responsibility for preparing j( y the NDT procedure deviation.
\ 4.2.1 The Request for Procedure Deviation, Form FE-4-3, shall
,! , have, but not be limited to, the following information:
9' (1) Site, d (2) Procedure Number, (3) Procedure Section and Page,
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g (4) Deviation Number, s J i 1 w
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("~'s SOUTHWEST RESEARCH INSTITUTE '"'"**
- IX-FE-101-1 Ng
/8 7.C NUCLEAR PROJECTS OPERATING PROCEDURE September 1978 1]1 g .~ -" Page 3 of 5 (5) Date Requested, 3 ,
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Deviation Required (6)
, (7) Examination Areas Affected by Deviations, and Ags 3,
(8) Basis of Deviations.
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4.2.2 Deviation numbers shall be assigned by the Manager of
( Support Services and shall be in numerical sequence beginning with "1" for each procedure revision, i
3 % 4.3 The procedure deviation shall be qualified by either field use, d TN laboratory verification, or review by a qualified Level III individual, under the direction of the Manager of the Nuclear Field N 1 Services Section or his designated alternate.
(m)
V $ b 4.4 Upon qualification in accordance with Paragraph 4.3, and veri-3 fication that the procedure deviation is in compliance with the E applicable code /other requirements, the person conducting the
! technical review shall sign the deviation.
I N 4.5 The Manager of Quality Assurance, or his designated alternate, shall verify that the deviation is in compliance with this procedure and sign the procedure deviation as reviewed and approved a
S \ and forward to the Department Director, or his designated i alternate.
! 4.6 If approved, che Department Director, or his designated alternate, E f shall sign the procedure deviation as approved and forward it to 2
che Manager of the Nuclear Field Services Section.
3 4.7 The final deviation shall carry the signatures as follows:
N (1) Reauested By. Requestor, if available to sign. If he is 2 not available, his name shall be typed in the " Requested M By" block.
(2) Technical Review. A technical review shall be conducted by D\ a person having an adequate understanding of the require-I N ments and intent of the deviation, who does not adminis-
! tratively report to the author, and is a representative of j
the same group that performed technical review of the r
s affected procedure.
5..a s s om G A. 3 1 s
O SOUTHWEST RESEARCH INSTITUTE 1x-FE-tot-1 September 1976
! NUCLEAR PROJECTS
/ y OPERATING PROCEDURE Page 4 of 3 "W
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gs (3) Approved By. Manager of Quality Assurance, or his desig-nated alternate. <
W., I p (4) Approved By. Department Director, or his designated \.
alternate.
T%' 4.8 The Manager of the Nuclear Field Services Section shall forward l .' the original Request for Procedure Deviation, Form FE-4-3, to
& the Nuclear Field Services Section file and a copy to the
% initiating Section Manager or team leader.
. 4.9 The requesting team leader may use the deviation of Nuclear g Field Services Section operating procedure upon receipt of e the final approval deviation and site approval of the deviation.
4.10 The deviation number shall be recorded in conjunction with the p y% appropriate NDT procedure number en all records requiring the 3 recording of procedure number, 4.11 A copy of the Request for Procedure Deviation, Form FE-4-3, shall
$, be attached to the applicable procedure when conducting exami-s nations in accordance with the deviation.
. # 5.0 RECORDS E W k 5.1 Operating procedure deviations and any other documents generated in accordance with this procedure controlling the performance of onsite critical services shall be retained for the period
}, 3 specified in the contract with the Client. These records shall W\
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be indexed, filed, and maintained in the Data Storage Facility of the Quality Assurance Systems and Engineering Division.
t 5.2 The Manager of Support Services shall be responsible for storage anc retrievat of documents generated.
o 5.3 A copy of the approv~i deviation on Request for Procedure Devia-
{
tion, Form FE-4-3, shall be forwarded to the Manager of Quality Assurance for the historical file.
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SevRI Form QA.31
IX-FE-101-1 September 1976 Page 5 of 5
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s 3 PROCEDURE DEVIATION W , , ,
,l 1 . - SITE 8 PROCEDURE / REVISION NO.
CEV!ATIO N N O. PAGE DATE REOUESTEDs SECTION 8 PAGE u
- OF OF
. rvawue a . a ens seeem er oevtsitew . ust enn seeettie ere s er cem eenee t te se e nemised is eneres e.
anta taas sesserien ( state e s e mene tien p ersed , sempement ide ntifiseff en , lin e identificetten , w eld identiflgeste. ,
w etc. )
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SOUTHWEST RESEARCH INSTITUTE $""d*1$1-1 O S*P'*"D** 1978 NUCLEAR PROJECTS Min L.R y a7 a=
3% OPERATING PROCEDURE -
Page Ja at5
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- ' l@f EFFECTIVITY s
S' $ .evision 1 of this Procedure became effective September 1976. Revision 1 consists of the pages, changes, and revisions listed below.
L 3 Page Number Change Revision Effective Date e
$ l-2 0 1 September 1976 j ( 3 1 1 September 1978
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4-5 0 1 September 1976
"(, ' Sa 1 1 September 1978 1
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SOUTHWEST RESEARCH INSTITUTE June 1980 NUCLEAR PROJECTS '
e OPERATING PROCEDURE 1l -
N Page 1 of 5 alN ONSI""E NDE RECORDS CON'"ROL
. W k 1.0 PURPOSE This procedure describes the onsite control processes for nondestructive 3
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, examination records (data) generated in the field during preservice and inservice examinations.
3 I SCOPE AND APPLICATION
} %2.0 2.1 i This procedure is limited to describing the flow of data g records used to document the resul:s of the nondestructive jg
3 examinations performed. Data records include Original Data Sheets , Su= mary Sheets , Resolution Sheets , s trip charts ,
magnetic tapes, video tapes, or other information as defined by the Inspection Engineer or Team Supervisor.
I < e D 3 4 2.2 Where necessary to explain the fl'ov of the records, functional j \ steps are provided in this procedure.
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$ q% 2.3 This procedure provides guidance to personnel of the Nuclear y s Field Services Section who are assigned the responsibility of preparing, reviewing, or othervise using data records while in
, q the field performing a preservice or inservice exa=ination.
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"$ 3.0 RESPONSI3ILITY j (1) The Director of the Depart =ent of Engineering Services, Quality I
j h Assurance Systems and Engineering Division, shall be respon-i 4 sible for the preparation, review, approval, and control of l this procedure.
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l -2 (2) The Manager of the Nuclear Fiald Services See: ion, ::epart=en:
)
of Engineering Services, shall be responsible f or :he i=plenen-stion of :his procedure in accordance vi:h :he Nuclear Quali:y 3 h Assurance Program Manual (NQAPM) specified in the applicable
( 4 SwRI Project Plan.
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(3) The Inspection Engineer shall be responsible for imple=en:ing g the require =ents of and ensuring compliance with this
= 4 procedure.
- 5. D I s I (4) The Manager of Suppor: Ser rices , Quali:7 Assurance Syste=s and l
) Engineering Division, shall be responsible for storage of
' records generated in accordance vi:h .his procedure.
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SOUTHWEST RESEARCH INSTITUTE June 1980
@ NUCLEAR PROJECTS g Ah' OPERATING PROCEDURE
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$lM PROCIDURE
- 4.0 i'
0 4.1 Orizinal Data Sheets s
I (1) Original Data Shee:s are originated when : hey are printed and serialized either a: SwRI or the site.
{. i. i (1) Original Data Sheets shall be filled out at the place j and ti=e of the e7=-inacion. '
k (3) The Original Data Sheets are returned to the tean staging area (office, ::ailer, etc.) on a periodic basis
,: (at neal eine, at the end of the day, upon leav1=g con-3 l. C trolled areas during an ISI), and an en:ry shall be ade
~$ in':o a daily log indicating tha: :he exanisations have been perfo med.
< T (4) *he Original Da:a Sheets are then placed into :he To-Be-Reviewed file.
q (5) The 3eviev Process is perforned as follows:
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(a) ~he Original Ca:a Sheets shall be checked for A'
N coupleteness and, to the extent practicable,
,& accuracy and consistency of :he da:a.
5 $4 If clarification or cor ection of any entry on (b)
N the Original Data Sheets is required, the
}. E Original Daa Sheets are returned to :he j @ Tv= miner.
(c) Af ter clarifications or correc:1ons , if any, are
,! T nada, the Reviewer shall sign each Criginal Da:a d Sheet that does not contain indica: ions which require evaluation /resoluzion.
.5 5 3 (6) *he Ori;inal Data Sheets : hat have been reviewed and 4 signed are noved to che To-Be-S e rized file. See 1 Paragraph 4.1(9).
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NUCLEAR PROJECTS OPERATING PROCEDURE
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(7) Original Data Shee:s which contai ' indications requiring
{ evaluation /resolu: ion are placed in the To-3e-Resolved CM file.
(a) Original Da:a Sheets in :he To-3e-Resolved file P 4 which docu=en: visual or surface exa=ina: ions are j { - handled as follows:
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(1) The Original Data Sheets are reviewed,
) g signed by the Reviewer, and used to gener-7 a:e a Cus:cmer Notification For: (CE).
(~"he CE is completed according to f NQA? 13-1).
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~hl (2) Copies of Original Da:a Shee:s shall be
_ade and at: ached to the CE.
s ; (3) A log shall be =aintained of CEs issued and their sta:us.
g g (4) The Original Data Shee:s are : hen placed s in the To-3e-Su==a:1:ed file. See
?aragraph 4.1(9).
,Q (b) Original Data Sheets in the To-3e-Resolved file j $ which docu=en ultrasonic exed-ations shall be M used to resolve the indica 1ces accordi:g :o N Paragraph 4.3 and then processed as specified in
.! l1 Paragraphs 4. l(5) and 4.l(6).
=, (3) If a ec=puter is being used :o re:ord resul:s and gener-j ate S m :7 Shee:s, cc pu:e: 1:pu: will be =ade. he
,1 computer vill genera:e :he Su==ary Shee:s a: :he co=ple-tics of all required exa d =:1ons of an - *-=: ice area.
8J 2 Y (9) If the compu:e is =c: used :o generate Sm:y Sheets ,
4 data placed in the To-Be-Sm:1:ed file is su==arized g
f according to Paragraph 4.2 and filed with the S' - s y Sheet in :he original data volu=es.
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} 4.2 S m rv Sheets i %
B Q (1) Su==ary Sheets are origi:a:ed whe they are pri=:ed and serialised either at SuRI or the si:e.
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O SOUTHWEST RESEARCH INSTITUTE m -tot-t
, June 1980 m
Lb NUCLEAR PROJECTS
%g OPERATING PROCEDURE Page 4 of 5 2l%
(2) Sary Sheets sha'.1 be filled out for each examination
{ area. In certain cases (studs, nuts, etc.), one Su= nary C ' Sheet =ay be used for = ore than one examination area.
(3) ~ S a r7 Sheets are to be filled out prior to the comple-
%, tion of si:e activities for each examinatica area for j y which examination requirements have been cocpleted.
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3 (4) Su==ary Sheets shall be filed with the data in the g original data volumes.
4.3 Resolution Sheets Y
j Q (1) Resolution Sheets are originated when they are printed and serialized eitner at SwRI or on the site.
tl (2) The Level II or Level III shall take the steps necessary
< D to resolve the ultrasonic indications and complete a j j Resolution Sheec describing the results of his analy-Any additional docu=entation required to suppor:
-M sis.
Ib the resolution will be attached.
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( (3) Original Data Sheets and resolution records with indica-tions requiring ne further action shall be placed in the
, Q To-Be-Reviewed file and processed as specified in Paragraphs 4.1(5) and 4.1(6).
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(4) Data with indications requiring further action will be j handled in a =anner established by the Director of the
.! Depart =ent of'F.ngineering Services.
e 1 %
j T 4.4 Strip Charts, h gnetic Taces, Video Taces
,,' y'. . (1) Strip Charts, Magnetic Tapes, and Video ~ apes are generated during sechanized ultrasonic examinations.
. ?
2 3 (2) As the charts and tapes are generated, they are iden:1-V fled with a sequence nu=ber and with the examination l areas for which they con:ain data.
1
, (3) During the resolution of any indica: ions, the strip j tj charts and tapes may be used by the Level II or Level
! y ul.
Nw (4) Tne strip charts and tapes are then =ade ready for transmit:al to 3wRI.
s.a ,w- ca.2 5
!\
SOUTHWEST RESEARCH INSTITUTE x + tot-t h NUCLEAR PROJECTS
/S. # OPERATING PROCEDURE Q#-?&
s Page 5 of 5 M } -
5.0 RECORDS j' ,
C' 5.1 Prior to departing from the site at the completion of a pre-s service or inservice examination, the original data package with the exception of scrip charts , magnetic tapes, and video 37 ; capes shall be reproduced and copy (ies) transmitted to the
> appropriate site personnel. At no time will data be reproduced C(N '
for this transsittal until the required examinations for a 3 particular area are complete, the data reviewed, and the
} Su= mary Sheets have been completed.
5.2 At the end of the site activity (or at other eines deemed
,y appropriate by the Inspection Engineer or Ieas Supervisor), the 3 4 original data package vill be transmitted to SwRI in accordance vich SwRI Operating Procedure X7II-AG-101-0.
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SOUTHWEST RESEARCH INSTITUTE 4 April 1980
!S - NUCLEAR PROJECTS i i OPERATING PROCEDU9E Page 1 of 12
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%A CONTROL OF NUCLEAR INSPECTION EOUIPMENT AND MATERIALS 1.0 PURPOSE o
y E h 1.1 The purpose of this operating procedure is to provide control for 5 the storage, inventory, issue, shipment, and return to stock of b yk
}
i examination equipment and materials.
SCOPE AND APPLICATION Q 2.1 The scope of this procedure is the control of nuclear examina-
{ D tion equipment to ensure the integrity of equipment and mate-1 0 rials used during the examination of nuclear power plant com-
)1 ponents. See NPOP VII-AG-102 for control of Search Units.
I 2.2 Controls are further required to ensure that maximum utiliza-
! $ tion is made of available equipment, i.e., equipment is hot " lost"
_c
'V in the Radiation Control facility, delayed or misplaced during 1
g transit from job site to maintenance shops, or allowed to remain 4
j out of circulation 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).
D
- 9 .3 This procedure is applicable to, but not limited to, control of the 3 following equipment and materials
j (1) Ultrasonic Examination Materials and Equipment I
L% J (2) Plastic Wedges N Penetrant Examination Materials j (3)
- )
(4) Magnetic Particle Examination Materials and Equipment
. N Eddy Current Examination Equipment and Standards j (5)
(6) Mechanized Examination Equipment C
(7) Data Acquisition Systems 5=
2.4 The following documents form a portion of this procedure as g applicable.
$was F orm QA.31
O SOUTHWEST RESEARCH INSTITUTE nu-Ac-t01-1 g April 1980
& . NUCLEAR PROJECTS t R. - OPERATING PROCEDURE U@Q Page -,, or. 12 i UN
{l 2 4.1 SwRI Nuclear Quality Assurance Program Manual (NQAPM) .
n SwRI Radiological Health and Safety Manual.
[ 2.4.2
! , I 3.0 RESPONSI3II.In 4 3.1 The Vice Presiden: of :he Quality Assurance Systems and Engineering (5N Division sail designate one or more secure areas :o be used f or g equipment and =aterials storage as control facilities.
S' 3.2 Control f acill:1es shall be operated by a Stock Clerk and an
, c Equipment Clerk under the supervision of the Manager, Support j lt-Ql Services, who will be responsible f or inventory, storage, issue, and retrieval of controlled equipment.
3.3 Responsible users, such as Team Supervisors, shall be r'sponsible e
5g for compiling a list, using SwRI For= SS-17 Equipment Control /
jl Shipping List (A :achment 2), of equipment and materials required
- for each job or project. They shall be responsible for shipment of the equipment to the job site, security while at the job si:e, f
reshipment upon completion of the job, documentation of faulty s[,
equipment, and tur=-in of equipment and unused materials.
,, 4 3.4 "'he Division Heal:h Physicist or his representative shall be j responsible for accepting equipment re:urned from an inservice w{- examination, its decontamina: ion, and returned to its proper i storage facility.
.Q4 The Manager, Desigm Engineering and Fabrication, or hir alternate gy 3.5 shall be responsible for providing mi,1-um main:enance turnaround
- ime and for providing current certifications as required for jl s nuclear exrmina: ion equipment.
Ml w 4.0 PROCEDURE
=
d I' ' 4.1 New Eouitment U.
4.1.1 Newly purchased or fabricated critical equipment shall be g inspected in accordance with SwRI Operating Procedure y g' VII-AG-101 prior to being routed to the appropriate con:rol j facility.
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O J SOUTHWEST RESEARCH INSTITUTE m t-^c- o -
April 1980 NUCLEAR PROJECTS wb OPERATING PROCEDURE uu;= Page 3 of 12
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, 4.1 2 An identification number (serial number) will be assigned to noncapital equipment which does not have a manufac-O( s turer's serial number.
4.1.3 Upon completion of proper identification, new equipment i N< will be listed on the control facility inventory records.
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T 4.1.4 Once new equipment is properly identified and inventoried, it will be issued to the appropriate maintenance facility j- for an operational check and certification in accordance u '
with NQAPM Procedure NQAP 10-1. The maintenance facility will return the equipment, along with copies of certif1-cations generated, to the control facility. The new equip-j g ment may then be issued for nuclear inspection work.
4.2 Equipment and Materials Issue p 4 4.2.1 When it is deter =ined that equipment and/or materials are j to be removed fro = the appropriate control facility, with hl the exception of equipment routed through the maintenance facilities (Paragraph 4.6.3), the Team Supervisor or
- i Responsible User will compile a list of required equipment and materials needed using Form SS-17. The responsible i supervisor shall complete each blank at the top portion of
,% the form with no exceptions. On the second part of the j p form, he will list quantity and nomenclature of each item M of equipment or materials required and ladicate those which
, i require certifications.
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4.2.2 Enen the Team Supervisor or Responsible User has initiated Form SS-17, he may assign any technician to draw and pack j the equipment. The technician will present Form SS-17 to
,! "%, the appropriate control facility, and the Clerk will issue o the material or equipment. The Clerk will enter appro-priate serial number and estimated replacement cost of each
. item on Form SS-17 as the equipment is issued. He will 5 -
also supply copies of appropriate certifications as d required.
,/ 4.2.3 When requested equipment and =aterials have been issued, g the technician will sign each Form SS-17, indicating that
{
l gx* he has received the items for the responsible supervisor, l
j and shall notify the QA Section so they can review the E' equipment and certifications.
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swr t Form G A.M
IIS^-
O SOUTHWEST RESEAPsCH INSTITUTE April 1980
$ NUCLEAR PROJECTS
/ ,-h OPERATING PROCEDURE I
Page 4 of 12 UlM 3 N h 4.2.4 "he Equipment Clerk will forward Copy 1 of Form SS-17 (white) the Shipping Agent, vill give Copy 2 (yellow) to the person signing the form, and will retain Copy 3 (pink)
' }t for his records. Copy 4 (goldenrod) vill be given to the QA Representative.
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4.3 Eculement Packing and Shiocing 4 i c
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4.3.1 If the equip:ient and/or =aterials are to be shipped from the Institute grounds, the technician vill pack each item g in numbered shipping containers. He vill then enter the container number in the appropriate Box No. space on
{ Form SS-17.
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- 4.3.2 If the equipment is to be shipped by freight, a box cous:
=ust be made and each box =ust be weighed. Shipping labels must be completed and affixed to each shipping container.
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When the packing.has been eo=pleted, the technician vill return Copy 2 of Form SS-17 to the responsible supervisor who retains this copy for accountabili:7 of equip =ent while i
in his possession.
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. 3.4 If equipment is to be shipped by f reight, the responsible i 4 supervisor vill contact the Requis1:1oning Agent, who vill 0
h<-,
arrange for shipping and for the proper shipping docu=ents to be completed.
' L 4.3.5 The responsible supervisor vill reviev Torm SS-l~, vi:h
(
~p special e=phasis placed on ensuring that appropria:e certi-i fications are available for each 1:e= that requires i certification.
4.4 Onsite Control
.N 4.4.1 The Team Supervisor or Project Engineer shall assume 3
~
l responsibili:7 for the security of equipment once it has been drawn from the control facility. A: the job si:e, he
-ill obtain a secure area to be used for equipment storage H and vill arrange for issue of the equipment er =aterials as
$ ,j the work load de= ands. He vill ensure that equipmen
! ', placed in:o ensite storage af ter use is dry and clean and 5, , that any equipment da= aged or found :o be inoperative or s, out of tolerance is tagged with a Form SS-19, " Hold Tag",
.D to indicate its condition (Attach =en: 3).
Swas poem G A.J.4 1
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C SOUTHWEST RESEARCH INSTITUTE hange 1 XIII-AG-101-1 L L NUCLEAR PROJECTS October 1980 OPERATING PROCEDURE UO, , . ; Page 5 of 12
$ D 4.5 Deconramination
-. Nx 3 g 4.5.1 Equipment being returned from an inservice inspection must be delivered to a radiation control area immediately upon return to the Institute. This equipment will be controlled 3
in accordance with SwRI Radiological Health and Safety p Manual, Paragraph 5.2.
5 -
4.6 Ecuipment/ Material Turn-in 0 4.6.1 Upon completion of a project or the return to the Institute of equipment used off the grounds, the equipment and/or unused materials will be returned to the control facility.
{ 10 (See Paragraph 4.6.2 when returning from an inservice exa=-
0 y ination.) As each item is checked in, the Equipment Clerk will enter the date in the appropriate remarks block of copy 3 of the Form SS-17. He will also initial in the appropriate remarks block of copy 2 of the Form SS-17 when 3 requested.
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} 4.6.2 Equipment and material being returned from an inservice y examination =ust be delivered to a radiation control area immediately upon return to the Institute. The Health Phys-l icist representative will inventory equipment and material
. and acknowledge responsibility for it. Equipment and mate-rial that is not contaminated or that is decontaminated 0 will be returned to the storage facility according to 4.6.1 and 4.6.2 above. Equipment that cannot be decontaminated i %; will be stored in the appropriate control area and the Health Physicist representative will inform the Manager, g
Nuclear Field Services, and the Equipment Control Clerk in writing of the nomenclature and the serial number of the
[g equipment, and the site the equipment came from.
4.6.3 F.xpendable materials such as Penetrant Examination Material
,g and Magnetic Particle Examination Materials will be 3 k returned to the stock room. W en the Stock Clerk can deter-
~
h mine that the material has not been used and identifying data is available to trace the material to the appropriate S certificates and to the original purchase order, he will credit the appropriate job site by processing an appropri-
= ate store requisition.
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S wa s srorm GA.3 4
SOUTHWEST RESEARCH INSTITUTE n n -Ac-tot-1 April 1980 9 NUCLEAR PROJECTS
. b OPERATING PROCEDURE y&, m*
Page 6 of 12 M$ 4.6.4 The Equipment Clerk will check each ites for disposition.
g Equipment requiring repair, cleaning, or recertification/
n, recalibra: ion within the nex: 30 calendar days must be
- w. accompanied by a Form SS-19,, Hold Tag (Attachment 3); and f taken to the appropriate maintenance facility.
3 <
! 4.6.5 Wen repair and/or certification is completed, the item 0 d will be returned to the control facill:y and placed in h stock for reissue.
u hd 4.7 Soecial Issue Recuirements s \
g 4.7.1 Occasionally it will be necessary for a Team Supervisor who j er.h) is in the field to request that equipment be checked out and sent to him. Wen this circumstance arises, he will i contact N nace andthe F.xamination
=ake Activities his needs known. The Coordinator or his alter Examination Activities I N Coordinator or his alternate will initiate Form SS-17 and j< -
g y draw, pack, and ship the equipment. He vill perform the review and enclose Copy 2 of Form SS-17 in the shipping
! container so : hat the Team Leader will have a record of d k what was actually shipped.
4.7.2 If equip =ent is to be shipped from one job locatica to
,g another without returning to the Insti:ute, a packing list will be ade using Form SS-17. One copy will be retained j
je p
,4 by the responsible person making the shipment, one copy will be enclosed with the shipment, and one copy will be
) ]h
. returned to the control facility at :he Institute. The A responsible supervisor will review :he Form SS-17 to ensure
- E that certificates were included as required.
I s J
} 4.8 Lost or Destroyed Eouipment
[
g! 4.8.1 In the event any item other than normally consumable = ate-
. rials is lost or destroyed while it is signed out of the
- ! 4]
% control facility, the responsible supervisor will ini:iate N a memorandum addressed to the Manager, Nuclear Field Ser-vices, and :he Manager, Design Engineering and Fabricatica, I A with a copy to the Manager of Suppor: Services. The memo-g randum will iden:1fy the equipment and describe the circum--
stances involved with its loss or destrue:1on.
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i' O~ SOUTHWEST RESEARCH INSTITUTE x m _ic_101_1 re NUCLEAR PROJECTS April 1980 gig OPERATING PROCEDURE
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Page 7 of 12 l lY 7 4.9 Recall of Eouipment for Recalibration 4.9.1 When notified that a particular piece of equipment is due recalibration, the Equipment Clerk will determine the location of the equipment by reviewing his equipment 3' j inventory records. If the equipment is located within the r .j stock room, he will place a " Hold Tag" on the item and take d' ,
the equipment to the appropriate certifying facility. When h the equipment has been issued, he will notify the Field 7 Services Activity Coordinator or other responsible super-I visor by completing a Form SS-42 (Attachment 4). The g Activity Coordinator or responsible supervisor will ensure e the equipment is sent to the Equipment Clerk on or before
{ the recalibration date. The Equipment Clerk will then p, place a " Hold Tag" on the item and take it to the appro-priate certifying facility.
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A Note: If a particular piece of equipment is being used in (j
' $ a non-critical application, it need not be returned until completion of the project.
k l j- 5.0 RECORDS
\ 51 Copy 3 of Form SS-17 shall be maintained by the control facility
, 4e for a minimum of six months af ter the last item on the form was turned in.
~
3 4 5!
] 5.2 SwRI Form SS-42 may be destroyed upon return of equipment to the t
.h stock room.
k i 5.3 The Equipment Clerk will maintain a file of current equipment cer-
= l tification records. An adequate number of copies will be included
$, for issue during equipment issue.
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SOUTHWEST RESEARCH INSTITUTE m t-^
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1 C SOUTHWEST RESEARCH INSTITUTE xttt-^o-tot-t April 1980
., NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 12
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This Form is a 4 copy form, Page 1 is white, page 2 is yellow, j , page 3 is pink, and page 4 is goldenrod.
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(] Attachment 2 swr 8 Form G A.31
SOUTHWEST RESEARCH INSTITUTE n:t-^c-to -t k NUCLEAR PROJECTS
' ' ", , OPERATING PROCEDURE Page 10 of 12 lhi I' ,
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SOUTHW.EST RESEARCH INSTITUTE April 1980
, NUCLEAR PROJECTS i OPERATING PROCEDURE
- "" Page 11 of 12
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RE C ALIB R A TION NOTICE
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j Recalibration Notice (SwRI Form SS-42)
O SveRI F orm QA.3-1 Attachment 4
SOUTHWEST RESEARCH INSTITUTE IIII- AG-101-1 i
NUC1. EAR PROJECTS October 1980 OPERATING PROCEDURE t d Page 12 of 12 UN g EFFECTIVITY PACE h Revision 1 of this Operating Procedure became ef fective in April 1980.
3, ,( Revision 1 consists of the pages and changes listed below.
6 Y 0 Page Nu:sber Change Revision Effective Date
, 1-4 0 1 April 1980 v 5 1 1 October 1980 l . 6-11 0 1 April 1980 12 1 1 October 1980 i
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O ' SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS XVII-AG-101-1 d' OPERATING PROCEDURE January 1981 Page 1 of 7 Titie -
DATA STORAGE AliD RETRIEVAL EFFECTIVITY AND APPROVAL Revision I of tnis procecure became effective on 2/10/S1 This procedure consists of tne pages anc changes listed below.
Page No Change Date Ettective 1-7 0 2/10/81 1
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l SA Acorovals b written By Date Tecnnical Review Date e dIhn 7/ ~ sf7 hl Mar 7ger of CLA. Da'te Cognizant Directer Date
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9 SOUTHWEST RESEARCH INSTITUTE January . 981 F
/q k NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 7 y4 i
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 Aeolication 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 f or 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.
I 9 5=Mt Form o A-3 2
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SOUTHWEST RESEARCH INSTITUTE January 1981 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 7 1.3.2 The Data Control Clerk of Support and Administrative Services shall be responsible for controlling, filing, and maintaining documentation covered by this procedure in the 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.
('
l .3.5 The Manager of Quality Assurance, or a designated repre-sentative, shall routinely audit performance against the requirements of this procedure and shall report the results of such audits to the Manager of Suppot: and Administrative Services and the Vice President, Quality Assurance Systems and Engineering Division.
1.4 Data Storage Facility Description The Data Storage Facilities for SwRI-retained quality assurance records are located in Building 124 and Building 139. The con-struction of Building 124 is concrete block with a steel door entrance. The construction of the facility in Building 139 is con-crete block with steel vault door. Both f acilities have tempera-ture control devices to regulate temperature and humidity.
2.0 PROCEDURE 2.1 Examination data and related material being sent to SwRI will be listed on For= 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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O SOUTHWEST RESEARCH INSTITUTE xvtr-AC-iot-1 p January 1981 k$g _gf NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 7 l
l 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 Su==ary 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 Entrv (3) Descriotion of Material. Analog and video tapes and strip charts will identify the examination to which they relate and will be numbered. Th is 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 reacter 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.
2.5 Items being removed from the Data Storage Facility shall be signed out. Original field data vill 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 arrangements 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 shall be responsible for its safekeeping and return.
Swal Form oA 3-2
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SOUTHWEST RESEARCH INSTITUTE January 1981 NUCLEAR PROJECTS OPERATING PROCEDURE 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
~
envelcpes 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 respectiva 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 thorter than the time specified in the applicable contract.
N'./ 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 cf 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.
n s=At Form QA.3 2
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SOUTHWEST RESEARCH INSTITUTE January 1981 I
k NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 7 l
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 certifica tions Zero reference location
'Jeld 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 inf ormation that would be of value Lifetime in conducting future ISIS s-Re poem QA 3 2 e
O SOUTHWEST RESEARCH INSTITUTE m t- a-lol-1 January 1981 NUCLEAR PROJECTS OPERATING PROCEDURE
.a (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 inrormation that will not provide Destroy after 2 years valuable information in conducting future ISIS 1
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l APPENDIX B
! SOUTHWEST RESEARCH INSTITUTE i I I i NONDESTRUCTIVE TESTING PROCEDURE i
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APPENDIX B SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURE !
Table of Contents Procedure No./Rev. Title 900-2/7 Visual Examination of Nuclear Reactor Deviations 1 & 2 Internals by Direct or Remote Viewing f
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PROCEDURE DEVIATION gm Il' y'd 33TE' PRCCCURE / REVISICN NC.
Pilgrim Station 900-2/7
.. CEVIATIO N N o. PAGE CATE RECUEST C s SECTICNs PAGE l
a 3 1 1 er 1 5 August 1981 5.1 2 CF 6 l
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E Visual Exasination of Core Spray Sparger Co=ponents to be conducted during i3 the 1981 inservice examination of Pilgrim Station and utill:ing SwRI-NDT-g 900-2/7 will be affected by this deviation.
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d , Change paragraph 5.1. "?ersonnel Certification" to read as follows:
Personnel perforsf r.g examinations shall be certified in accordance with N SwRI NQAP 11-2, Revision 2, " Procedure for Certifying Visual Examination Personnel."
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l for visual examinations.
m
O V PROCEDURE DEVIATION
- h. . m..
t l #"Z7 SITE' PROCEDURE / REVISICN N O.
Pilgrim Station 900-2/7 CEVIATIO N NO. PAGE CATE RECUESTED SECTICN PAGE
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, Visual Examination of Core Spray Sparger Components to be conducted during 2 the 1981 inservice examination of Pilgrim Station and utilizing SwRI-NDT-3 900-2/7 will be affected by this deviation.
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- n. u.4 it .. u.,y 3 Change paragraph 6.2.2 to read as follows:
j 6.2.2 Resolution v Resolution shall be considered adequate when:
- s 4
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(1) The combination of access, lighting, and angles of vision,
. either unaided or corrected, can resolve a black line 1/32-inch 3 wide on an 18% neutral gray card placed on the surface to be j examined, or for the examination of core spray spargers the follow-ing shall apply; .
$ (2) the intent of NRC Bulletin 80-13 is met such that the limit of h'N
% resolution is determined by fine wires of .001", 004", or .006" nominal diameter superimposed upon the area of interest.
.ae Change paragraph 6.3.1 to read as follows:
,' Resolution shall be considered adequate when:
h 9
$ k (1) The combination of access, lighting and angles or vision, either
~
g unaided or corrected., can resolve a black line 1/32-inch wide on an 18% neutral grey card placed on the surface to be examined or
\. in a situation similar to the area to be visually examined, or
?~ for the examination of core spray spargers the following shall a 3g apply;
~
(2) the intent of NRC Bulletin 80-13 is =et such that -$e li=1t of 1 resolution is determined by fine wires of .001", v04", or 006" nominal diaceter sueerimoosed ueon the ares of interest.
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. e a 3 This deviation is necessary to meet the requirements of NRC Bulletin 80-13.
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\'~'l ~2 SOUTHWEST RESEARCH INSTITUTE %"ls7%i March 1978
. '"1 CLEAR PROJECTS O,-i...ATING PROCEDUR E
- n. Page 1 of 6
$ T VISUAL EXAMINATION OF NUCLEAR REACTOR ISTTERNALS
- 5. BY DIRECT OR RE".0TE VIENING c
SwRI-ND'T-900-2 y N
!' .-' 1.0 PURPOSE N
j f This procedure provides the technical information and detailed steps t
% ,' required to ensure accordance proper with the visual ASME applicable examination of nuclear Boiler and Pressurereactor Vesselinternals, Codes.
. 2.0 SCOPE AND APPLICATION 1 j 2 Nuclear reactor internals as specified in the applicable SwRI Exanina-qion Plan shall be examined visually by direct or remote viewing.
& 2.1 Applicable Documents v -
i The following documents form a part of this procedure, as applicable:
- , 3 (1) ASME Boiler and Pressure Vessel Code,Section XI,1974 Edition, with Addenda through Summer 1975, " Rules for
.p Inservice Inspection of Nuclear Power Plant Components."
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Edition, with Addenda through Su=mer 197S, " Nondestructive l Examination."
] (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) .
i 3 3.0 RESPONSIBILITY
[ (1) The Director of the Department of Engineering Services, Quality Assurance Systems and Engineering Division, shall be responsible i T 2
7 for the preparatien, review, approval, and control of this procedure.
(2) The Manager of the Nuclear Field Services Section, Depart =ent of 4 Engineering Services, shall be responsible for the implementation J
! ! of this procedure in accordance with the NQAPM specified in the jy applicable SwRI Project Plan.
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som aroe m o,a 3-1
SOUTHWEST RESEARCH INSTITUTE S27%-'~2 March 1978
!_$ , NUCLEAR PROJECTS g3 9 OPGR ATING PROCEDURE il -.a 2" Page 2 of 6
$ 7 The examiner shall be responsible for implementing the require-hb
, (3) ,
i ments of this procedure. l Q !
s (4) The Manager of Support Services, Quality Assurance Systems and T, Engineering Division, shall be responsible for storage of records generated in accordance with this procedure.
5 4.0 CODE AND PRCCEDURE REQUIRESENTS 1 2:
{ g The following is a guide to the requirements for this procedure.
Requirements Section
, e 3 y (1) Personnel certification 5.0 S
(2) Equipment 5.0
% Surface condition and cleaning
( (3) 6.0 i% requirements Id 1 'i (4) Examination method 6.0
% (5) Lighting requirements 6.0 m (6) Resolution 6.0 3 *)mk (7) Examination areas 7.0 5 'I 5.0 PERSONNEL AND ECUIPSENT j
. 5.1 Personnel Certification A Personnel performing examinations shall be certified in ccordance with SwRI NQAP 11-1, "Special Process Control."
w 7 5.2 Equipment C V S
The Visual Examination Acceptability Test Card shall be made from Kodak Neutral Test Card No. R-27 or an equivalent, with an 18's neutral I grey side having a 1/32-inch wide black line down the center.
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SwHe Form G A 3-4
O SOUTHWEST RESEARCH INSTITUTE i d ;7 5 March 1978
-2 i NUCLEAR PROJECTS OPERATING PROCEDURE a Page 3 of 6 Q W Commercially available equipment shall be used as required for the per-i % formance of examinations by the techniques described in Paragraphs 6.2
% and 6.3.
% 6.0 EXAMINATION METHOD Lg j k 6.1 Surface Cleaning
-N 3 Visual examinations which require clean surfaces or decontamina-h N' tion for valid interpretation of results shall be preceded by appropriate
%g h eaning processes.
, M Examinations may be required where the surface is painted or has j other types of coatings. This shall be permitted if it is determined that
[X such coatings do not interfere with valid interpretation of results.
@ 6.2 Direct Visual Techniaue
< D 3 Direct visual examination shall be performed by placing the eye s" s within 24 inches 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 3 such as magnifying lenses may also be used.
D 6.2.1 Lighting h In addition to the general lighting, illumination of the area N
to be examined shall be provided at right angles and oblique angles to expose cracks or evidence of corrosion or erosion.
I
} 6.2.2 Resolution I
- i Resolution shall be considered adequate when the combination of 3 access, lighting, and angles of vision, either unaided or corrected, can resolve a black line, 1/32-inch wide, on an IS% neutral grey card placed on
, the surface to be examined.
6.3 Remote Visual Techniaue Remote visual examination may be used when conditions exist i that do not permit direct visual examination. Remote visual examination may
- j include visual aids such as telescopes, periscopes, borescopes, fiber optics, a -
bi G SwAl Form QA.31
SOUTHWEST RESEARCH INSTITUTE S*"t-""?
Revision e -2 O
March 1978
. NUCLEAR PROJECTS D OPERATING PROCEDURE
'D" Page 4 of 6 m
v U or TV cameras and monitoring systems, with or without attachments for pema- l g j nent recording. Remote techniques shall demonstrate the ability to provide I cg '
a resolution at least equivalent to that obtainable by direct visual examina-tion. Mirrors, movable lights or rotating optics, or any combination thereof, may be employed to display cracks, surface scratches, or evidence of corro- i 5lY, sion, erosion, misalignment, or movement. !
6 Sk 6.3.1 Resolution s >
i
?,
Resolution shall be considered adequate when the combination access, lighting, and angles of vision, either unaided or corrected, can i
resolve a black line,1/32-inch-wide, on an 18% neutral grey card placed on j the surface to be examined or in a situation similar to the area to be i visually examined.
?
S 6.4 Replication
, Surface replication techniques shall be considered acceptable
$ provided the surface resolution is at least equivalent to that obtainable by
? the direct visual technique.
I '
j 7.0 EXAMINATION AREAS d Section XI of the ASME Boiler and Pressure Vessel Code requires y visual examination as a part of the inservice examination requirements j4 in order to provide a report of the general condition of the reactor "C pressure vessel internals. This report shall include such conditions as wear, cracks, corrosion or erosion on the surfaces, or misalignment or
[
movement of the internals.
~i %
The areas to be examined shall include major load bearing elements j '
of the reactor internals which are relied upon to retain the core structure i
~i 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 cperation, and the critical j locations on reactor internal compcnents as identified from the vibration analyses, and the interior of the reactor vessel for evidence of loose parts or foreign material.
, Components, parts, and method of examination shall be as specified in j' the applicable SwRI Examination Plan.
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n U SOUTHWEST RESEARCH INSTITUTE t"l15?-2 March 1978 NUCLEAR PROJECTS
/3 D'
- 4 OPERATING PROCEDURE Page S of 6 8
0' S. 0 RECORDING CRITERIA 2
3 g*
k Visual indications shall be recorded on the "SwRI Visual Examination Record" and reported to the customer.
3 % The completed "SwRI Visual Examination Record" shall contain, but not i q be limited to, the following information:
5 NN iI (1) Identification of the examined part and the extent of the I
h%
examination, including surface preparation, if required.
h (2) Method and techniques used in the examination. This shall include visual aids, if used.
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7 (3) Examination results with location and a description of any S indications.
O c' Q (4) Name and certification level of personnel performing the examination.
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) (5) Time and date of examination.
9.0 EVALUATION Evaluation of reportable indications shall be the responsibility
{ g of the customer, or the customer's representative, in accordance with Article C o IWA-3000 of Section XI of the ASME Boiler and Pressure Vessel Code. The
- applicable year of the Code and Addenda shall be as specified in Paragraph 2.1(1) of this procedure.
5 Y 10.0 RECORDS j
The customer shall receive copies of documents generated in accor-dance with this procedure in the examination report.
y Permanent documents generated in accordance with this procedure shall 3 , be stored and retained as a portion of the examination report. The examina-
~
&j tion report shall be stored by the Manager of Support Services, Quality Assurance Systems and Engineering Division, in the Data Storage Facility for the period specified by the contractual agreement with the customer, s
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i CERTIFICATES OF PERSONNEL QUALIFICATIONS i
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APPENDIX C ,
CERTIFICATES OF PERSONNEL QUALIFICATIONS Table of Contents Personnel VT Page Reaves, L. C. II C-1 Shimkus, R. P. III C-2 C-1
SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION 3< 9 STATEMENT OF CERTIFICATION J
The Director of the Department of Engineenns Senncee. Queety Assurance Systems and Engmeenng Civeson, cornfies that Larry C. Reaves ;,q m ,, % II . y.m ygg ,,,.
, VT-1. VT-2, 3' ~
in accoroance wrth the requerements of SwRl Nuclear Questy Assurance Procedure 11-2. Reveson 2.
Caranceaan umstanone:
None ,,
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Exowsoon Om:
10/21/84 //yk,,, f
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Saned:
Qwector, Department of
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- i. EDUCATION. TR AINING AND EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TR AINING (the mothod and leved:
High School Bass H.S. (Ga) 5 GRAD oste Comoweed: 08/02/79: 10/16/81 l North Georgia College 2 NO g,,,,, 3: u g,,,,,, hH M or r. sed of Study Physics Ft. Carson School of Aeronautics - 1 year 0eto Emoloyed by swr 1: 02/20/78 p,,,,,,, u o e ,,,,n.nc, ii, ,,,o ,,, ,,,,,i,,,,,,;
The indhndues has been credited with 7 monthe of empenence in the exammedon method on to date of certficanon. Some of the exponence may have 3
been accrued samultaneously with other NCE methode (at least 25% wee in the method).
VISUAL ACulTY AND COLOR PERCEPTION The mdiv.dualis cacable of readmg Jaeger Number 1 letters at 12 inchee, and is caoeole of reading Sneden NumOer 30 letters at a destance of 20 feet. in at leset one eye (ussng correcove lenses if specrfied beeowl. and can distingush and differentiate contrast between colors used in the method.
Corr. Corr.
Cate Rec. Venfled by Date R eg. Venfied by 08/03/81 No Heidi Gutierrez &
f MOST RECENT EXAMINATION GR ACES CERTIFICATION HISTORY: THIS LEVEL Scores Weeght Date Go..er=#: 92.50 .33-1/3 ina Cartincano,,. 09/04/79 Soectne: 87.50 .33-1/3 g,,,,,,,,,,,,,; MMUM Prach. 81.33 .33-1/3 g,,,,,,,,,,,;
Comoomte:
37.11 1.O g,,,,,,,,,,,,
Recernneanon:
oats: 10/16/81 djaMd R ,,,,,,,,,,,.
Resoone.b= Levee m. Stanlev M. falker REMARKS i \
SwRI Form CA-424 C-1
m 4, 3 SOUTHWEST RESEARCH INSTITUTE R' + .
NONOESTRUCTIVE EXAMINAT10N f,j 7 STATEMENT OF CERTIFICATION
- , v
'w The vici P'emdent. Cuanty Assurance Systems and Engineenng Civison, cartrftes met Robert P. Shimkus b auanned as teves ill in visuas Teseng tvTI, catesones Vt-1, VT-2 VT-3 VT-4 in accordance witn ene requirements of Swai Nucteer Quauty Asaurance Pmcedure 112. Revemon 2.
Ca- s Limitacons: None Emperacon Cate: 09/02/84 Sign,J: M '
Cate:
hent. CuantCAssuranca dystems and Engmeenng Cmson y' ECUCATICN ANC EXPERIENCE MISTCaY l EDUCATICN: NAME YEARS CEGREE Prevois NCE excenence sit used for cuauficanon):
Hign Scnoas MarcelluS H.S. (Mich) 4 GRAD com ,,n, ,,, 7, Accmonas Michigan State Univ. 4 B.S. Reoublic Steel Coro. 1948 1952 Goodvear Aircraft Coro.1952 1953 Craft Metal Fabrictg.Co.1953 1955 Masor Feed of Study Meta 11urrical Eneineerine Goodvear Aeroscace Core.1958 1968 Westincheuse Electric lens i970 uts Emoioved ev S=AI: 01/06 / M De incivicuae nas oeen crecited witn at ieast 396 monen,et,,=enene, in :nes examinanon metnoo an tne care of cern6 canon. Sorne cf tne emoenence may aave :een accrueo simustineousy tn orner NCE metnoos ist
' east 23*% aos in tnis mornoo).
VISUAL ACtJITy ANC CCtCR PERCi?T1CN Tho individual is cacaose of rescing Jaeger Numcor 1 !etters at 12 kicnes, and is cacaede of rescing Snelen Numoer 00 fetters at a cistance of 20 feet, in at least one eve lusng correc=ve tenses if scacrfied benowt, anc can cisanguesn and cifferentate contrast terween cotors used in tnis metnoc.
Carr. Carr.
Oct) eec. Ven6ed5v ,, Oate m ec. Venfieo my 10/03/80 1
Yes Heidi Gutierre: gla 19/23/81 Yes Heidi Gutierrez y; c.T I vCST eeCsNr Ex Aumar:CN aa4CES I CsaTmC2r:CN mSTCav- m S trvet Scores W egnt Care Cen= s: 88.05 0.5 n,n,,c.,uge.non: 01/02/74 soecine: 92.22 0.5 e ,c ,,,,,c,,,n ; 01/02/77 p,.cuc24: N/A N/A pecern6 canon- 01/02/80 Comoost2: 90.14 1._. 0 ,,c,,une non; 09/02/81 accertticanon:
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wAt Form CA.s34 C-2 i
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APPENDIX D FIELD MEMORANDUM TO BECo AS AMENDED AFTER REVIEWING COMPUTER-ENHANCED PHOTOGRAPHS TO: Frank Famulari Boston Edison Company ,
Pilgrim Station DATE: 9 October 1981 FROM: R. P. Shimkus SwRI
SUBJECT:
Preliminary Report of 1981 Remote Visual Examination of the Pilgrim
- Nuclear Reactor Core Spray Piping and Spargers 1.0 SCOPE Perform a remote visual examination of the subject reactor component. ,
The examination is to meet ASME SEction XI Item Bl.15 and Category B-N-1.
In addition, the examination is to address the NRC Bulletin 80-13 requirement for a visual resolution of a 1-mil wire placed in the examination area.
2.0 EXAMINATION w/
The examination was performed in accordance with- the Southwest Research Institute (SwRI) Examination Plan prepared for Project 17-6676 (81-BEC-PPS-1-1-0) approved by Boston Edison Company (BECo). The resulting data was evaluated by the writer, a Level III visual examiner qualified by experience and written examination. Reexamination and surface cleaning was ac:omplished as considered necessary for indication resolution.
3.0 EXAMINATION RESULTS 3.1 Resolution of 1980 examination indications on Lower Sparger i
3.1.1 "B" sparger, nozzle 40B. 1980 examination showed HAZ linear indications (see Figure 1). The 1981 examination resolved these as resulting from grinding to remove weld l undercut (see Tape 10). The 1980 examination equipment did not permit viewing the indications from the nearly vertical position. The resulting oblique lighting cast a sharp nar-row shadow (linear indication).
3.1.2 "B" sparger, nozzle 41B, see Figure 2. Same as 3.1.1.
3.1.3 345* Header-to-sparger pipe weld and area out to nozzle 25 on the "B" system. The 1980 examination showed many linear indications (see Figure 3). The 1981 examination exhibits
/~'T the same characteristics as in 1980 (see Tape 8 count 330-(m / 413 and tapes 9 and 10). There is no continuous crack-like indication extending from over the top of the sparger i
D-1
piping to underneath the same pipe. A fine line appears on the header-to-sparger weld, but because the weld is thicker than the sparger pipe wall, it would not normally be con-sidered significant (a crack).
3.1.4 165* Header, "D" sparger, header-to pipe-weld. The linear indication found during the 1980 examination is no longer l visible (see Figure 4). The 1980 indication is believed to l have been a shadow.
3.2 Upper Sparger 3.2.1 15* Header, "A" Sparger, header-to pipe-weld linear indi-cation observed during the 1980 examination was found using computer enhancement techniques (see Figure 5). It appears to have stabilized with respect to crack growth. There was no indication that the crack extended into the upper quadrant.
3.2.2 The transverse indication on pipe 1"-12" towards 270* from the "A" sparger header observed during the 1980 examination has been resolved as not significant (see Figure 6), (see tape 8, count 413-453). This indication has been shown to have no depth when viewed close up normal to the pipe.
3.2.3 195* Header, "C" sparger,1/2" to 1" f rom header-to-sparger weld on the pipe. The 1980 examination showed a linear indication extending vertically downward from an are strike (see Figure 7). No linear indication could be found during the 1981 examination. The area was wire brushed and reexamined (see tape 10). No linear indication could be resolved.
4.0 CONCLUS!ON Five of the indications from the 1980 examination have been resolved as not significant. Two were determined to be heavy grinding, one was determined to be a mechanical mark, and one of the indications could not be relocated (found).
One area, "B" header-to pipe weld and the area to nozzle 25B was deter-mined to have undergone no change since the 1980 examination. Cracks appear in the upper quadrant but are not shown to be present in the lower quadrant. This area has stabilized with regard to crack propagation and further area degradation is not anticipated.
The HAZ indication (crack) reported in 1980 on the "A" Sparger was relocated using computer enhancement techniques. The crack appears at about 4 o' clock and extends downward and out of sight. There is no O
D-2
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g indication that the crack extended'into the visible upper quadrant. This i crack appears to have stabilized and further degradation is not expected.
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-$ 0 db&xo R. P. Shimkus 1 ,
i Technical Consultant !
', Southwest Research Institute I t i
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j FIGURE 1. "B" SPARGER 1980 INDICATION FIGURE 2. "B" SPARGER 1980 INDICATION 1981 RESOLVED AS OVER GRINDING 1981 RESOLVED AS OVER GRINDING
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,l "B" Sparger 90' Side Out to g
, Nozzle 25B Appearance of a Mechanical Mark FIGURE 3. 1980 CONDITION 1981 NO CHANGE FIGURE 4 "D" SPAPGER 180* SIDE 1980 CONDITION
, 1981 INDICATION FOUND BY
, Indication COMPUTER ENHANCDENT TECHNIQUES e
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" A,, FIGURE 5. "A" HEADER 90* SIDE HEADER 0%m0N 1981 INDICATION NOT FOUND Pipe l2 Indication h \
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i FIGURE 6. "A" SPARCER 8"-12" ON 270* SIDE OF HEADER 1980 CONDITION 1981 CONDITION IS THE SAME. RESOLVED AS MECHANICAL MARK.
FIGURE 7. "C" HEADER 270* SIDE 1980 CONDITION "C"
1981 INDICATION NOT FOUND BEFORE OR HEADER
- AFTER WIRE 3 RUSHING Arc Strike i= -Indication O _
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APPENDIX E REFERENCE SHEETS RELATING 1980 TO 1981 I
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November 6, 1981 l
l Southwest Research Institute 6220 Culebra Road San Antonio, Texas 78284 ATTN: Mr. W. T. Flach
Dear Mr. Flach:
Enclosed please find copies of photographs taken from the video tapes of the 1981 remote visual examination. Please evaluate these indications as soon as possible.
If you should have any questions please contact me immediately.
Sincerely, ME F. N. Famulari Operations Q.C. Group Leader FNF/pb enc 1.
Sfs 4WM SWdd5 g gog3 f 290674 M lWOWNS g[
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APTECH ENG RING l SERVICES v. ,
793 SAN ANTONIO ROAD PALO ALTO, CAUFORNIA 94303 i
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