ML17348A320
| ML17348A320 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 05/22/1990 |
| From: | Anderson E, Matley J, Moaba J FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17348A319 | List: |
| References | |
| ESIG-PTN-88-08, ESIG-PTN-88-08-R00, ESIG-PTN-88-8, ESIG-PTN-88-8-R, IEB-88-008, IEB-88-8, NUDOCS 9006260058 | |
| Download: ML17348A320 (148) | |
Text
JUNO NUCLEAR ENGINEERING EQUIPMENT SUPPORT & INSPECTIONS GROUP 0 700 Universe Juno Beach, Blvd.
Florida FINAL REPORT OF ZNSERVICE INSPECTION NONDESTRUCTIVE EXAMZNATZONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88 08 PREPARED BYC FLORIDA POWER AND LIGHT COMPANY FOR TURKEY POZNT NUCLEAR POWER PLANT UNIT NO+ 3 PoO ~ BOX 3088 FLORIDA CITY'LORIDA 33034 COMMERCIAL SERVlCE DATE 14 DECEMBER 1972 NRC DOCKET NUMBER: 50-250 DOCUMENT NUMBER ESIG-PTN-88-08 REV. 0 REVISION NO ~ : DATE: 05/22/90 PREPARED BY: DATE / / 1 Sr. Specialist ISI REVIEWED BY: %san DATE: '~/ v f~~+
SUPERVISOR - CODES &
PROGRAMS GROUP APPROVED BY: DATE:
MARA R EQUIPMENT UP ORT & INSPECTIONS 9OOC i9 9 00626O O'OOCK, O~ O50OO250 PDP PDC 9
v e ivW y 0, 0 < ~ vr 'F t I v th) PIP ~~ra h
tSffl'ur f '~, v 4'pl ( f" Y1 p( e w a ~ t4 ~
FINAL REPORT OP INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 TABLE OP CONTENTS TITLE PAGE/COVER SHEET......... ......... .......... 1 TABLE OF CONTENTS. ~ ~ ~ ~ ..... ........ ........... ....
~ ~ ~ ~ ~ 2 RECORD OF REVISIONo ~ o ~ ~ ~ ooo ~ oooo'.os ~ .o...o....o ~ ooo. 5 ABSTRACTo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 6 ABBREVIATIONS... .......... ........................... 7
1.0 INTRODUCTION
. ~ ......
1' PROGRAM APPLICABILITY. ~ ~ ~ ...... ~ . ~ ~ .... ~ . ~ ~ . ~ ~
1.2 INSPECTION INTERVAL...........................
1.3 INSPECTION ..
~
PERZODS ~ ~ ~ ~ 8 1o4 APPLICABLE DOCUMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~ ...... ..... ~ ~ ~ ~ ~ ~ ~
1.5 APPLICABLE CODE EDITIONS AND ADDENDA..... ~ ~ ~ .. 9 2 ' ENGINEERING RECOMMENDATIONS ~ ~ ~ ~ .... ~ ~ ~ ..... ~ ~ . ~ . ~ . 10 2.1 CHARGING PUMP' TO PRESSURIZER AUXILIARY SPRAY LINE ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 2 ' CHARGING PUMP TO "C" HOT LEG.. ~ ~ . ~ ~ ..... ... ~ ~ ~ 10 3.0 ABSTRACT OF EXAMINATIONS PERFORMED ... .... ... 11 3.1 APPLICABLE AREAS............ ........... ... ~ 11 3.1.1 AUXILIARY SPRAY LINE........ .......... 11 3.1.2 CHARGING LINE ............- . ...... 11 o rvttt ' 't, o oqwtr't'p goose 'tO " o o r o I,r It ww o e "t t' r't'
FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 TABLE OF CONTENTS 3.2 LIQUID PENETRANT EXAMINATIONS................ 11 3 ' ULTRASONIC EXAMINATIONS. ....... .........-.. 11 4.0 ABSTRACT OF CONDITIONS NOTED..................... 12 4 ' AUXILIARY SPRAY LINE... ~ ...... ....~ ~ ~ . ~ . ~ ~ ~ .. 12 4 '.1 2"-RC-1310-1. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . 12 4 '.2 2"-RC-1310-2 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ - ~ - ~ ~ . 12 0 4.2 CHARGING 4.2.1 LINE..... . .
3"-CH-1301-42.........................
................... 12 12 4.2.2 3"-CH-1301-43......................... 12 5.0 CORRECTIVE ACTIONS TAKEN AND/OR RECOMMENDED...... 13 6.0 EVALUATION CRITERIA............................. 14 6 ~ 1 CLASS 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 14
- 6. 1. 1 ACCEPTANCE STANDARDS FOR CLASS 1...... 14 7.0 INSERVICE INSPECTION
SUMMARY
TABLES............. 15
7.1 DESCRIPTION
OF TABLES....................... 15 7.1.1
SUMMARY
PLAN TABLES EXPLANATIONS..... ~ 15 8 ~ 0 RECORDS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 16 e
~ ~q -~.py>@pe veywvq"P,h, y" q>> ~ >>m.~,w. ~i+s ~>>... ypr:r,
~ ~ ~, ~~.>>>>, w, i'm;ir ieger~>>
v
FINAL REPORT OF INSERVICE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE 'IPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO+ 88-08 8 ~ 1 GENERAL. ~ ...... ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ................
REPORTS' 16 8 ' INSERVICE INSPECTION
SUMMARY
~ 16 8.3 SPECIAL REPORT........ '6 APPENDXCES A REFERENCE DRAWINGS............................... 17 B PERSONNEL CERTIFXCATIONS ~ ~ ~ ~ ... ~ ................. 18 C ULTRASONIC EQUIPMENT. ~ .. ~ ~ ~ ... ~ ~ ~ . ...........
~ 19 D ULTRASONIC TRANS DUCERS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ .. ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ . 20 E ULTRASONIC COUPLANT. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 21 F THERMOMETERS ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 22 G LIQUID PENETRANT MATERIALS ~ ~..................... 23 H EXAMINATION PROCEDURES I ULTRASONIC CALXBRATION BLOCKS J LIQUID PENETRANT DOCUMENTATION DATA PACKAGES 26 K ULTRASONIC DOCUMENTATION DATA PACKAGES..... '27 L ENGINEERING RECOMMENDATIONS DOCUMENT SE&PT-SSAD-7814........................... ... 29 M NRC BULLETIN 88-08 THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS... .... ..... 30
FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMZNATZONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88 08 RECORD OF REVISION REVISION DESCRIPTION OF REVISION DATE APPROVALS NUMBER REASON FOR THE CHANGE REVISED
2
'I+l I
'l h
A
, I C
II t
f 'Ar 4 ' "9 t y
FINAL REPORT OP ZNSERVICE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88 08 ABSTRACT This document describes the Inservice Inspection results of Nondestructive Examinations performed during the 1990 refueling outage which began on February 6, 1990. This document addresses the nondestructive examinations performed, conditions noted and corrective measures recommended or taken as required by ASME Section XI 1980 Edition through the Winter 1981 Addenda, IWA-6220.
This document addresses NRC ACTION ITEM 2 and the reporting requirements as identified in item 4 of the Action Requested by the Nuclear Regulatory Commission.
This report documents the examination activity performed on Florida Power and Light Company Turkey Point Nuclear Power Plant Unit No. 3.
There were no indications that exceeded the acceptance crite-ria of the ASME Boiler and Pressure Vessel Code,Section XI.
~tl1 iv .~ '\ ~ IVY to\ 'Vr w ~ I rt i n t, V t 4 p '~ ~IP '
hW~ 'lE t4 I 4 +'+Ph%+l' .'p'P 'E.'%, V; gpp,$ $ J
FINAL REPORT OP INSERVICE INSPECTZON NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 ABBREVIATIONS LISTED BELOW ARE THE ABBREVIATIONS UTILIZED IN THIS DOCUMENT ASME AMERICAN SOCIETY OF MECHANICAL ENGINEERS B&PV BOILER AND PRESSURE VESSEL CODE C&P CODES AND PROGRAMS GROUP CH CHARGING ESIG EQUIPMENT SUPPORT & INSPECTIONS GROUP FP&L FLORIDA POWER AND LIGHT COMPANY ISI INSERVICE INSPECTION JUNO NUCLEAR ENERGY SERVICES MATERIALS, CODES AND INSPECTIONS SECTION NDE NONDESTRUCTIVE EXAMINATION NUCLEAR REGULATORY COMMISSION PTN-3 TUEKEY POINT PLANT UNIT NO. 3 RCS MAIN REACTOR COOLANT SYSTEM RC REACTOR COOLANT I I,'* Q, Jt 7 6 << I I1 C * - 0 l ~
0 '~$t I 1 Vlhh .fV Tt h fh ~ IVI,T>>.,P g<<l
~ t>> fl 9g V tVP ~
Wf IPW Wl 'W
P 1
3 k
4 C
C C
I I
P l
4 i I ~, tr g +,'t +',"tel r" 'i e w'tw wgwl<e~+8,55"4+5 l 'p <<';,' '~, l" r f ss ~x'gaga'+pl
FINAL REPORT OR ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO 88-08
1.0 INTRODUCTION
1.1 PROGRAM APPLICABILITY This Report details the Florida Power & Light Company's results of Inservice Inspection, Nondestructive examinations performed at the Turkey Point Nuclear Power Plant, Unit No. 3.
1.1.1 The operating License for Turkey Point Unit no. 3 was issued on April 10 1973, and Florida Power and Light Company is the owner of record.
1.2 INSPECTION INTERVALS The Second Inservice inspection Interval became effective on February 22, 1984 and ends on February 21, 1994.
1.3 INSPECTION PERIODS The Inspection .Interval is divided into three successive inspection periods as defined by Program "B". The NDE examinations were conducted in the Second Inspection Interval, Second Period and the Fourth outage.
~ Period START END February 22, 1984 September 21, 1987 NOTE: Extended the period in accordance with IWB-2412 (b) inorder to enable the inspections to coincide with a plant outage.
September 21, 1987 February 22, 1991 3 February 22, 1991 February 21, 1994 1.4 APPLICABLE DOCUMENTS The Nondestructive examination Program performed during this activity was developed after giving due consideration to the following documents:
FINAL REPORT OF 1NSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTZAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO+ 88 08 ej ASME BOILER AND PRESSURE VESSEL CODE g SECTION XIg 1 98 0 EDIT ION THROUGH THE WINTER 1 98 1 ADDENDAg RULES FOR ZNSERVZCE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS" U. S. NUCLEAR REGULATORY BULLETIN 08 TITLED "THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMSn DATED JUNE 22~ 1988~ SUPPLEMENT 1 DATED JUNE 24'988 AND SUPPLEMENT 2 DATED AUGUST 4g 1988
- TURKEY POINT UNITS 3 AND 4 (NRC BULLETIN 88-08 THERMAL STRESSES IN, PIPING CONNECTED TO REACTOR COOLANT SYSTEM)
ENGINEERING DOCUMENT FOR THE IDENTIFICATION OF UNISOLABLE PIPING AND DETERMINATION OF INSPECTION LOCATIONS, DOCUMENT NO: SE&PT-SSAD-7814, DATED: AUGUST 1988 Letter L-88-558 dated December 30, 1988, Florida Power
& Light. (FPL) discussion of plans to have flow tests performed to demonstrate that these conditions are unlikely at Turkey Point Units 3 and 4.
- Letter L-88-436 dated October 14, 1988, Florida Power &
Light Company (FPL) responded to action items 1 and 2 of the bulletin, and providing the results of FPL review for Turkey Point Units 3 and 4, and a plan and schedule for completing the non-destructive examination (NDE) required by the bulletin.
Letter L-89-176 dated May 4, 1989, Florida Power &
Light Company (FPL) report of non-destructive examina-tions performed on Turkey Point Plant Unit 4 and the results of the flow testing and the conclusions reached.
1.5 APPLICABLE CODE EDITIONS AND ADDENDA As required by Title 10 of the Code of Federal Regulations paragraph 55a (g) (4) Znservice Inspections requirements applicable to nondestructive examination at Turkey Point Unit 3 are based on the rules set forth in the 1980 Edition of Section XI through the Winter 1981 Addenda, hereafter referred to as the Code.
FINAL REPORT OP ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFPECTS REPERENCE NRC BULLETZN NO ~ 88 08 2.0 ENGINEERING RECOMMENDATIONS Following is the engineering recommendations of areas were NONDESTRUCTIVE EXAMINATIONS were identified for potential thermal stress effects as described in NRC Bulletin 88-08.
The components subject to examination were determined to in-clude portions of the following lines:
2 ' CHARGING PUMP TO PRESSURIZER AUXILIARY SPRAY LINE
'k The 2 inch .weld on the 4" x 4" x 2" reducing tee at the Main Spray Line connection was recommended for examination as identified on isometric drawing 003-A31, and also, the weld at the outlet of valve 3-313.
2.2 CHARGING PUMP TO nCn HOT LEG Two welds at elbow to valve 3-312B as identified on weld location map 003-A44.
10 A pl P'I It " 9~ 0 Yffl 0 J '0 " I A %IN I P QuQ 1 '/8 lv
i.
~ ~ rest. +e i t, aY a, TPv P v Vr r pttw . z, 8'easy'31, pie p;1 +pe re+, ~
I ",0 ~+ p Y ~8 ~Pi PPV ws Pgf as
FINAL REPORT OP INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88 08 3.0 ABSTRACT OF EXAMINATIONS PERFORMED F 1 APPLICABLE AREAS Based on the recommendations identified in Section 2 following items were scheduled for nondestructive examination.
3.1.1 AUXILIARY SPRAY LINE DRAWING 003-A31 ZONE IDENTIFICATION DESCRIPTION EXAM METHOD 035 2n-RC-1310-1 TEE - PIPE UT & PT 035 2"-RC-1310-2 PIPE - VLV 3-313 UT & PT 3.1 2 CHARGING LINE LOOP C DRAWING 003-A44 ZONE IDENTIFICATION DESCRIPTION EXAM METHOD 045 3"-CH-1301-43 PIPE - ELBOW UT & PT 045 3rr CH 1301 42 ELBOW - PIPE UT & PT 3.2 LIQUID PENETRANT EXAMINATIONS The Liquid Penetrant examinations performed were conducted in accordance with FP&L NDE procedure 3.3. This procedure complies with the ASME Code. The examinations performed were required by Table IWB-2500-1 and FP&L intends to utilize the examination records for ASME Code credit and are part of the Inservice Inspection Program.
3.3 ULTRASONIC EXAMINATIONS The ultrasonic examinations were not required by the ASME Code Tables IWB-2500-1 due to the size being 2" and 3".
The supplemental examinations were conducted. in accordance with standard piping techniques for the 3" charging system. For the 2" Auxiliary Spray system a new NDE procedure (NDE 5.19) and calibration block (UT-54) had to be written and fabricated for the examination of the socket weld areas.
e
~ l 4 g "' Q *' ' "', ~" ~ t thgt Ee' ' 0 ~" 4 g( f P p" i ' ' ' ll u ~ ' IPPC 5' t" I+V)tf
I
'I 4
J 0
I 1
} 8( A g fl 'V' - ' ' '4 '
f '% '% I 4
' ' 4 '4 7 '
~ C' t g gp 2
FINAL REPORT OR ZNSERVICE ZNSPECTXON NONDESTRUCTIVE EZAMXNATXONS 0 OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTXAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO 88-08 4.0 ABSTRACT OF CONDITIONS NOTED Described below by component is a summary of conditions noted during the Unit No. 3 examination activity:
4.1 AUXILIARY SPRAY LINE 4.1.1 ZONE 035, 2"-RC-1310-1, Reducing Tee Pipe:
A liquid penetrant and ultrasonic examination using a 45 and 70 degree search unit was performed. ONE (1) geometric reflector was recorded and determined to be caused by the outside diameter. Confirmed by dampen-ing the surface.
4 ' ' ZONE 035i 2" RC 1310 2/ PIPE VALVE 3 313:
A liquid penetrant and ultrasonic examination using a 45 and 70 degree search unit was performed. One (1) geometric reflector was recorded and determined to be caused by root geometry.
4.2 CHARGING LINE LOOP C 4 2 1 ZONE 045 3n CH 1301 42'IPE ELBOW A liquid penetrant and ultrasonic examination using a 45 and 60 degree search unit was performed. Three (3) geometric reflectors were recorded and deter-mined to be caused by root geometry.
4.2.2 ZONE 045, 3"-CH-1301-43, ELBOW - PIPE:
A liquid penetrant and ultrasonic examination using a 45 and 60 degree search unit was performed. Three (3) geometric reflectors were recorded and deter-mined to be caused by root geometry.
12
0 v I'1 .i+ - ' ~ - >- =,, ~ 'w g~,
+ %'"
g 1'\T +'+ C,", E" g.I tgP,Q'lM)lt
PZNAL REPORT OP ZNSERVICE INSPECTION NONDESTRUCTIVE EXAMINATIONS 0 OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EPPECTS REFERENCE NRC BULLETIN NO ~ 88-08
- 5. 0 CORRECTIVE ACTIONS TAKEN OR RECOMMENDED All indications noted were evaluated in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI (were acceptance criteria exists). There were no indications that exceeded the acceptance criteria of the ASME Code, IWB-3000.
13
1 J
J l
I$
~ ' t I' ) ~" t w'>n'v er e'g v wats>e~w+'mv>> ~<w<pgs <<y~rgny
> y>gp ~puv+',ecwy,e
PXNAL REPORT OF INSERVXCE INSPECTXON NONDESTRUCTIVE EXAMINATIONS OF UNXSOLABLE PIPXNG SYSTEM AND COMPONENTS FOR POTENTXAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETXN NO ~ 88-08 6.0 EVALUATION CRITERIA During Inservice Inspection, flaw indications are evaluated against the acceptance standards of the ASME Code as follows:
F 1 CLASS 1 6.1.1 Acceptance standards for class 1 are as follows:
EXAMINATION .COMPONENTS OR PARTS EXAMINED ACCEPTANCE CATEGORY STANDARD B-Z DISSIMILAR AND SIMILAR METAL IWB-3514 WELDS IN PIPING There were no Flaws identified during the examina-tion activity.
14
v t h e s t~, gEr t, r p p5y em+ ~ rim+ g +mfa%+ ~7 ~pl I' P ie~ OA/ tPhA<F'+<'Y 5 QQt'%~q 7p~
PZNAL REPORT OP ZNSERVZCE ZNSPECTZON NONDESTRUCTZVE EXAMINATIONS OF UNZSOLABLE PZPZNQ SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO 88-08 7.0 INSPECTION
SUMMARY
TABLES
7.1 DESCRIPTION
OF TABLES The TKGKY POINT PLANT UNIT 3 Inservice Inspection tables are summarized by code categories and code item numbers and provides the results of the FP&L examination activity that were performed on the Auxiliary Spray Line and the Charging Line.
7 ' 1
SUMMARY
PLAN TABLES The final report tables were developed based on systems and components which are subject to examination and include such information as follows:
(1) ZONE NUMBER - Components and or systems are divided into zones. Each zone is further subdivided by the following categories:
(a) ASME Code Category (b) ASME Code Item Number (c) ZONE Identification Number (d) REFERENCE DRAWING IDENTIFICATION (e) LINE ITEM NUMBER administrative number used for computer identification purposes (f) Examination Area Identification identifies the item or area to be examined (g) INSTRUCTIONS special comments that may be required for a specific item (h) RESULTS divided into four areas:
- 1. NOREC no recordable indications
- 2. INSIG when indications were observed that were below the recording level
- 3. GEOM was applied when indications which .
have a amplitude equal to or greater than 1004 of the DAC curve, and have been documented to be geometric in nature
- 4. OTHER are those indications evaluated to be other than insignificant or geometric (i) Examination Method to be used for the examination (j) NDE Examination Procedure to be used for the examination 15
I I
v ~ t<< - ~ w>t t>> ' (*We Y "s, hr we Y5r .wt s 4"; w" '
f Wf e st1
DATE: 05/18/90 TURKEY POIHT NUCLEAR PLANT UNIT 3 PAGE'5 A REVISION: 1 INSERVICE INSPECTIOH SPECIAL REPORT SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (1990)
CLASS 1 COHPLETED COHPONENTS 2 INCH REACTOR COOLANT H N I 0 ZONE NUNBER: 035 ASHE S ON 0 T SEC. XI T RSE H SUNHARY EXAHINATIOH AREA CAT0Y EXAII A E I 0 E REHARKS HUNBER IDEHTIFICATIOH ITEH HO HETHOD PROCEDURE T CGH R ~ICALI BRAT ION BLOCK~~
FROH PR SPR Y N TO " CMARG G N R F 0 HO 00 A3 102000 2"-RC.1310.1 8 J PT NDE 3.3 201 C C 2 16 90 PT EXAH CONPLETE REDUCING TEE TO - PIPE 89.40 UT 70 NDE 5.19-1 C *2-16 90 UT 70 DEGREE AXIAL O.D. GEONETRY UT-45 NDE 5.19 1 C 2 16 90 UT 45 DEGREE AXIAL SCAN COHPLETE
- UT-54**
102100 2". RC.1310-2 8-J i PT HDE 3.3.202 C C 2-16.90 PT EXAII COHPLETE PIPE - TO - VALVE (3 313) . 89.40 UT 45 NDE 5,19 2 C 2 16 90 UT 45 DEGREE LINITED TO .3" FROM UT 70 HDE 5 '9-3 C US SIDE TOE OF HELD 8 0"-1" CM AHD 0".'I" CCH. 2 16-90 UT 70 DEGREE CONPLETE UT 54*
yap. ~ s- v my, a ~ v rs,, >>" r, e iqt.w t'
e g ar;.~ i'~qpw ~armer, wi" yppwrr,, ~ w ~ i>>pig epg~eg w'~et TI "~rvpqv
DATE: 05/18/90 TURKEY POIHT NUCLEAR PLANT UNIT 3 REVISION: 1 INSERVICE IHSPECTIOH SPECIAL REPORT SECOND INTERVAL, SECOND PERIM, SECOND OUTAGE (1990)
CLASS 1 COHPLETED COHPONEHTS NCH C H CA 8 VO C TRO N C N I 0 ZONE NUHBER: 045 ASHE 8 ONG T SEC. XI T RSE H SUHHARY EXAIIIHAT I OH AREA CATGY EXAII A E I 0 E REHARKS NUHBER IDENT IF ICATION ITEH NO HETHOD PROCEDURE T CGH R ++CALIBRATION BLOCK
- FROH 29n R S HOT G TO R G N HT. EX REF DUG NO 003-A44 155300 3"-CH-1301.42 8-J PT NDE 3.3-230 C C 2-23-90 PT COHPLETE PIPE TO ELBOU 89.21 UT 45 NDE 5.4 44 2 24-90 UT 45 COHPLETE UT 60 HDE 5.4-44 2 24 90 UT 60 COHPLETE
- UT 53~~
155400 3".CH.1301.43 8-J ,
PT HDE 3.3-233 C C 2.22.90 PT COHPLETE ELBOH TO - PIPE 89.21 UT 45 NDE 5,4 43 2 24 90 UT 45 COHPLETE UT 60 NDE 5.4 43 2 24-90 UT 60 COHPLETE M-53**
0 a ~ 's ~ I
FINAL REPORT OF ZNSERVICE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 8.0 RECORDS
. 8.1 GENERAL Records of Inservice Inspections Plans, Outage schedules, Calibration standards, examination and test procedures, results of activities, final reports, certifications, corrective actions taken or recommended IWA-6000 will beof developed and maintained in accordance with the ASME Boiler and Pressure Vessel Code.
8.2 INSERVICE INSPECTION
SUMMARY
REPORTS Ninety days (90) following the units return to service MCI shall forward a summary report (NIS-1) of the ISI activity to the Nuclear Regulatory Commission in accordance with IWA-6220 8.3 SPECIAL REPORTS This report is prepared to meet the reporting action required by the bulletin and satisfy the FP&L requirements.
e 16
~
- a " w'rrw'~<<<<w ',w rc', tw ~ 'ze <<~,'r ~ " ' ~w-<<" ~" ~. <<s'a " 'w 'i 'w ' ~ w . rot ~ ec<<~wq
0 rye s ~ w + 'w s t'
FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE BXAMZNATZONS OF UNISOLABLB PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLBTZN NO+ 88-08 APPENDIX A REFERENCB DRAWINGS DRAWING NUMBER REV. NO. TITLE 003-A31 2" AUXILIARY SPRAY LINE 003-A44 3" CHARGING LINE 17
,I e
'I l
I 0
,p 't r w,t;,sv'r * " " ~e<g~f'Ps~% p< > 'I, 'w < ", 1w ' ~ 'wt lg$ egw(tp(4e'
4"-RC-1304 PRZ. SPRAY CONT. ON DWG.
ZONE 003-A14 020 rr Qi 3-313 Q2 4 X4" X2 RED. TEE 3/4 T-58 30 ANNULUS SIDE BIO SHIELD WALL PEN. A CONSTANT WEIGHT HANGER 3-SR-49 ~ U-BOLT RESTRAINT 3-RS-I I45 9 QA 28 RESTRAINT 45'OX REACTOR SlOE 31 27 25 3-SR-66
~ U-BOLT RES1RAINT 3-RS-2
/
45 SPRING HANGER 24 3 23 FLOW
~ 3-SR-43 O L PEN. B lll-~
16 SA MECHANICAL SNUBBER 3 -CH-1301 ,2 3-SR-47-C
~
CHARGING 3 VCH 118C 22 21 20 17 32 45m
/f)2 CONT. ON DWG.
ZONE 003-A44 045 BOX RESTRAINT MECHANICAL SNUBBER 3-SR-47-B ~i) tx BOX RESTRAINT 2 -RO-1210 3-SR-65 7
+2 XO REO. ~EL. 22 -0 19 U-BOLT 3-HCR-A dc ROO HANGER
~ 3-SR-47-A MECHANICAL SNUBBER 7 45m
~ 3-PS-592 MECHANICAL SNUBBER SPRING HANGER 3-SR-46 10 RIGID TELESCOPING STRUT SPRING HANGER 3-HGR-C 3-SR-45 ~ 11 45'H 12'3 HQK5'YSTEM IO: 041 6c 047 CVCS STRESS PROBLEM: PS-I/023 ~fLOW SPEC NO: 2 -RC-2501R-5 PA MATERIAL SPECS CODES dc PROGRAMS GROUP REFERENCE DRAWINGS PRESSURE dc TEMPERATURE STATS SIZE SCH TYPE TURKEY POINT UNIT 3 5177-102-SK-P-641 REV. D TITLE: 2 INCH AUXILIARYSPRAY UNE TO 5177-102-SK-P-639 REV. D DESIGN PSIG: 2485 TEMP(F): 650 2 160 A376 TP316 SMLS PRESSURIZER 5610-FSK-M-433 OPERATING PSIG: 2335 TEMP(F): 493 3/4 160 A376,TP316 SMLS 5610-M-410-202 SHT. 2 OF 2 DATE: 10-20-89 ZONE: 035 5610-M-420-214 SHT. 3 OF 3 HYDROSTATIC PSIG: 2624 TEMP(F): 547 REVISION APPROVED BY: DRAWING NUMBER:
5613-P-661-S REV. I SHT. 2/4 UT CAUBRATION BLOCK: N/A 4 , L. ANDERSON 003-A31
~ ~ t " .I g ~ 7 I> ~ w rg> r<< ~ e iS ... we e ~r; i w ~~pic, i ";.r: v'wptwl~;'V: ..P%t "p 'V) '9" <'tpjVP'7W'Y',"V."~'l C
1 BOX RESTRAINT 3-VCH-130 3-VCH-118A RIGID ROD 3/4 HANGER ROD HANGER 12 ANNULUS SPRING HANGER SIDE 3-VCH-131 3-VCH-114 I BIO SHIELD 29 -RCS-1308 45~ WALL MAIN REACTOR COOLANT BOX RESTRAINT 39 33 CONT. ON 3-PS-60
+34 003-A08 i
OWG.
4 36 ZONE 014 30 PEN. A~ BOX RESTRAINT
/ ~<o6, 13 45%
ANNULUS SIDE BIO RIGID TELESCOPING STRUT REACTOR 3-SR-39 40 45 10 SHIELD 44 SIDE WALL ROO HANGER EL 25'-7 1 2 9 8 3-VCH-132 7%
~
4 14 SPRING SUPPORT 43 3-SR-38 042 L. 23'-9 7 8-3/4 4W 3-31 28 PEN. NO. 2 15 REACTOR 3"-CH-1301 45'EGENERATIVE 16 HEAT EXCHANGER 0 18 CONT. ON 23 CV-3-310A ~17 DWG. 003-Vl1 ZONE 05g 22 3 -CH-130 O CV-3-311 24 I QB CHARGING 21 CONT. ON EL 15'-6" 2 X3 DWG. 003-A45 1 046 I'ONE RED. WELDED SUPPORT STANCHION 3-VCH-115 I QA 2 -RC-1310 k
AUX. SPRAY CONT. ON ~ 3-SR-64 SPRING SUPPORT
~
HQKS'YSTEM:
047 DWG. 003-A31 26 STRESS PROBLEM: PS-I/023 ZONE 035 PB SPEC NO.: 3"-CH-2501R CV-3-3108
~
2g 45'8 PIPE SUPPORT 5610-M-420-3 SHT. 3 3-SR-37 5610-M-410-91 SHT. 2 5613-P-661-S REV. 0 SHT 1 IL 2 OF 4 REFERENCE DRAWINGS PRESSURE Ec TEMPERATURE STATS SIZE SCH MATERIAL SPECS TYPE pp) Qe CODES dc PROGRAMS GROUP TURKEY POINT UNIT 3 5177-SK-P-639 REV. C TITLE: 3 INCH CHARGING LINE FROM RHX TO 5177-SK-P-642 REV. 0 DESIGN PSIG: 2485 TEMP(F): 680 160 A376 TP316 SMLS LOOP C HOT LEG 56'Io-M-420-214 SHT. 3 OF 3 OPERATING PSIG: 2235 TEMP(F): 653 E 2387-1C-297 DATE: 10-19-89 ZONE: 045 5610-T-E-4505 SHT. 1 HYDROSTATIC PSIG: 2335 TEMP(F): 547 REVISION APPROVED BY: DRAWING NUMBER:
5610-T-E-4501 SHT. 1 UT CALIBRATION BLOCK: N/A 4 E. L ANDERSON 003-A44
+'}) 6 I4 ~~ - t % "'y "t +g 'L t )5* + ~ - t ~ ', ' P \ ",, <f Pllpl(g $ Wp 'IP Quip, 7 C P *,gled tfhoglyJ +9=;-s A< 'I 4 c'i Wt >
f I. J y rTVtll PI iPe~
FINAL REPORT OP ZNSERVICE INSPECTION NONDESTRUCTIVE EXAMZNATZONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO 88-08 APPENDIX B PERSONNEL CERTZRZCATZONS NAME VT-1 VT-2 VT-3 VT-4 UT PT MT EYE EXAM, CARR, FRANCIS T. N/A N/A N/A N/A III III III 04-14-89 BRANNIN, MICHAEL N/A N/A N/A N/A IT IT N/A 09-08-89 KOVALOVICH, PAUL II N/A N/A N/A II II II 01-05-90 REDDING, CRIS N/A N/A N/A N/A II II II 02-02-90 I
ROBB NS I MICHAEL D II II II II II II II 08-09-89 VANO, RICHARD J. N/A N/A N/A N/A IT IT IT 09-11-89 18
JNS+I -9. 3 Revisi IVE HRHINATICN PEBSGNNEL CZRFIF IGG'ICN NhbR F. T. Carr IZNYIBlaSIINIZVHr.
EQQHINATICN b%?MD Liquid Penetrant LIMITATIQ6 HQHINATI(ÃREKKiIS:
(tenSm}
BAS IW GENERAL 80%
808 AIMINISIKHEDBY AQHINIS'IIHBZIBY
~
~ (~
<~
718}
I 'WIR ~
11/87 AIMINISYIHIHD BY Hellier Associates 1/88 SPECIFIC mCrlCAL 95%
100~ ADBINISIBISB) BY Hellie M~~ DARB OVIR I/88 PCS ITE 88.7SS (AVIRAGE CP ALL SK883) LEVEL III CNLY mmmrmx: (INVEIGLE CHmamICAL adam) lÃIKS NB. ADS.'IBIS SRIKO 12/80-Present 86 FPL; Level ZII, 1KB Engr., respansible for ZSX eeaminatian procedures and technical perfoaaance of nuclear a fossil NDE activities.
3/75-11/80 Huclear Svs; Dixector ZSI Eng., Iavel III responsible for ZSX masminatian procedures, techniLqu demQagnent, technical direction of field HDB exarainatica activities.
3/74-12/74 10 Offshore Pwer g Sect~ Mrg NDE Product~
re spans e or and technique development.
10/70-2/74 40 Seatrain Shi. g Mgr. QC 5 HOT Depte respans or cxmp te mspectian of super tanker (see attached resum. for additianal infarmatian}
4c CERTIFIED BY TITLEV.P. Nuc. Cyexatians ~TE ~p $ 6
'IBIS CZRI'IFICATICN IS VALID QTFIL Z "All historical information supplied by me to ecaqile this ertification is true and correct to the best of my knowledge" J
EXAMINEE .
J%+I-9.3 Revision 3 IVH HQMNATICN PEISC5NEL (XRFIFICATICÃ
?ybR Frank T. Carr QRCIPIGQ'ICSI LIMIL CZZ KNMINATICNbRBKD Ma etic Partic1e LIMITATICM None
~
EQMINATICN HRSIEH c BAS IC<< 80'8 AIMNIFIKREDBY (QA-718) D'YE U/87 AIMNIFIKKOBY ASAP JA-718 BASE 11/87 SPECIFIC 96% ACMINIBIIDIBDBY BeUAes AsseessSes BASE 1/88
'PRACTICAL 100% AIÃINIPIEFSSD BY Helliez Assccistes DIIE 1/88 CC5%'C6 ITE 89% (AVZmt:a Ce ALL SCam) <<LEVEL III C5LY EfHREBKZ:
e
( INVERSE CHRCSMGICAL CBKHt)
CRIES NS. AEB.'IHIB SECIYSS . CBPANY (IIKLUXYYSB CF SCSK AND MX IZVBL) 12/80-Pzesene 86 PPL. Level III, NDE Engr. respmsibie offornuclear ISI examination and technical perfozmance
& fossil NGE activities.
3/75-11/80 68 Nuclear Svsg Dixecf:or ISI Blg.g Level III xespons e or ISI emuainatian procahues, tecimiquc develogn nt, technical ~~ian of fie16 NER examination activities.
3/74-12/74 10 Offslxam Power stems. Sect~ Mgr. NDB Production e r ard tedmuye dee3xgnmt.
ENTITLE 10/70-2/74 40 Seatr;Lin Shi ; Hgr. QC & NOT Dept.
ccats ete ~pect~ of super tanker CENIIFIZD BY /4 Nu 0 r tf n WE 4-J4-
'IHIS CZRFIFICATICN IS VALID MFIL nager, MCI "All historical information supplied by me to compile this c tification is true and correct to the best of my knowledge" EQNNEE .
JNS+I -9. 3 Revision IVE EXAMINATE PEISCINEL CZRPIF ICATKH F. T. Carr CZRnFlmV1m LEVEL III EXAMINATICNbRIKD Ul trasonh c
~~
LIMITATIQ6 None EXAMINATKNRHSUGIS:
{3AS ICS'0% AIMINISTKHEDBY ASNT ( JA-718) BAYS ll/87 IIL AGCli K AKNT JA-7l8 MrE 11/87 II 11t A f Dl I/M PRACPICAL AIMINIS'IERED BY Eel I I sr Assecf aces MIK I/88 CRXQS ITE 82. 25K (AVERAGE CP ALL SCRIBES) tLEVEL II I CNLY EPERIBKE: ( INVERSE CHRQKGX'rICAL CRIER)
BAKE IO. sES.'IHIS 'ARIIIXI Q5PANY ( INCLUX TYPE CF MXK AND NDE 12/80-Present 86 FPL; Level III, NDE Engr. respons)ble for ISI technical performance examination procedures and of nuclear d fossil NDE act$ vft$ es.
3/75-11/80 68 Nuclear Ener Svs; Dfrector ISI Eng., Level III IZlfEL)'See respons e for I examinatfon procedures, techniqul development, technical d)rection of field NDE exam$ natfon act$ v$ t$ es.
3/74-12/74 10 0ffshore Power S stems; Sect)on Mgr. NDE Production respons e for procedure and technique development.
10/70-2/74 Seatra)n Sh) build)n Co ; Mgr. gC 5 NDT Dept.
respons e for comp ete nspect1on of super tanker construction.
attached resume for add)tional $ nformatfon)
CENTI IFIZD BY / Air TITLE V.P. Nuc. Operations RTE p-/4-REV IEWEO BY 'IBIS CZHTIFIC'ATICN IS VALID QFIL nager. MCI "All historical information supplied by me to ccayi this certification is true correct to the best of
/
and my knowledge" te a EEAMINEE
F. T. CARR REVi 4/84 NOE S ec1alist - Nuclear Ener Services West Yirgini a Inst1tute of Technology, Engineering and Business Administration 1965 - 1970 Oouglas Ultrasonics, Inc., Ultrasonic Technician with varied independent assignments worldwide.
1970 A.J. Testing Laborator1es, NOT Technician and Ultrasonic Speci al 1 st.
1970 - 1974 Seatrain Sh1pbui lding Corp., Supervisor and Manager of the gC inspect1on of Super Tankers. As the level III Supervisor my involvement started with the 1nception of this new Sh1pyard.
Our1ng my tenure, I bui lt a department of 40 Supervisors and Technici ans.
1974 - 1975 Offshore Power Systems, Section Manager, NOE production responsible for UT, HT, PT, and YT procedures and progranatic administration during the start-up of the construct1on of floating Nuclear power pl ants.
1975 - 1981 Oirector, ISI Engineering with overall management responsib1lity for 44 people 1n the production of Nuclear 1nservice 1nspection prograas, NOE procedures, technique development, and the field deployment of ex'amination personnel. My responsibility includes the training, certification, and administration of some 28 technici ans.
Level III (by exanination) fn UT, MT, PT, and VT aids my dec1sion making ability as the princ1pal authority for many company polic1es and project cemitments.
1981 - present florida Power and Light Company, NOE Speck ali st.
Amer1can Society for Nondestructive Testing - Sonics and Visual committee participation, past Chairman of the Metro-NY and Northeast florida sect1ons American Melding Society
CERTIFICATION 6'ERSONNEL QUALIFICATION
.'RAINING SUPPLEMENT
-'- NIK SCHOOL (PROGRAM) LOCATION GATE LENGTH SUB JECT W. Va'. Inst. of Tech Mont e WV 61 Branson Instruments St d Krautkramer Ultrasonics Richmond VA 2 68 40 hrs Basic U Norwich CT 5/69 24 hrs MT/PT/RT UT ET Krautkramer Ultrasonics Stratford CT 10/69 40 hrs Ultrasonic Weld I A. J. Testing Brookl n, nY 1970 40 hrs MT/PT/RT (OJT)
ASNT Teterboro, MY 1968 18 hrs MT/PT ASNT National Conference Detroit, MI 1972 32 hrs UT/RT/MT/PT ASNT National Conference Chicago, IL 1973 32 hrs UT/RT/MT/PT Kean College Union,,N.J. 1973 40 hrs UT/RT/MT/PT/ET Kean College Union, N.J. 1973 40 >rs Radiography (Level IE)
ASNT National Conference 'leveland, OH 1974 32 hrs Ultrasonics Nat iona 1 Conf erence Houston'X 1976 32 hrs Ultrasonics
'SNT Battelle-Columbus Labs Columbus, QH 2/78 40 hrs Ultrasonics-IGSCC Workshop ASNT National Conference Atlant , GA 1981 32 hrs UT/RT/MT ASNT Atlanta, CA 10/81 8 hrs Leak Testing ZETEC Miami, PL 5/82 hrs.
i 40 Eddy Current EPRI Charlotte,'C /84 40 hrs UT-Pled Sizing
~ Iooe ~Q'b INSPECTION PERSONNEL EYE EXAMtNATION t
y/ gl ~r)'/)
j7 QAt5~
iAST
/~W~
FI AST MI OOLE Lac st i att:
Without Glasses 0 Without Glasses With G lasses gjd;. Chart No. Snellen With Glasses Chart No. J1 Right Eye g OK 0 See Recommendation Right Eye 5l 'K 0 See Recommendation
',eft Eye df OK 0 See Recommendation Left Eye g OK 0 See Recommendation
. Eyes OK 0 See Recommendation Both Eyes g OK-, 0 See Recommendation Color Blindness ( 0 Isihara 0 Isochromatic ) - Write in Number Read 1 17 25 33
.,2 18 26 34 3 19 35 4 12 20 38 5 '13 21 37 6 14 22 30 38 15 23 31
~
16 24 32 Recommendation: See Physic~an stricted Fail Remarks:
~l /i est Administrator
~/c/-) /
~
applicant's Signature pate
<OTE: THE ABOVE P TA WILL MFET THE
~ SNT-TC-1A/ANSI N45.2.6 REQUIREMENTS LATEST REVISION.
Form 4aoatl,a rNontstockoo) Aev a/at
JNS-QI-9 ~-
Revision NONDESTRUCTIVE EXAMINATION PERSONNEL CERTIFICATION NAME CRIS M. REDDING EXAMINATION METHOD ULTRASON C LIMITATIONS CONTACT TECHNI UES ONLY EXAMINATION RESULTS BASIC+, ~NA ADMINZSTERED BY DATE (METEOD*)GENERAL ~86 ADMINISTERED BY . . CARR DATE ~1 ~8 SPECIPIC ~82 ADMINISTERED BY F T ~ CARR
~ DATE ~11 22 89 PRACTICAL ~00 ADMZNISTERED BY F. T. CARR DATE ~01 30//0 COMPOSZTE ~89.3 'AVERAGE OF ALL SCORES) +LEVEL ZIZ ONLY EXPER1ENCE 6 (INVERSE CHRONOLOGICAL ORDER)
DATES NO ~ MOS THIS METHOD COMPANY INCLUDE TYPE OF WORK AND NDE LEVEL 10/89 ~F g Level IZ ISZ Technician performing Present Nuclear Fossil Plant NDE.
2/87 10/89, 32 EBASCO Services Xnc.; Level ZZ ISI Technician performing PSZ & ISZ examinations at a variety of assignments.
6/85 - 7/86 13 World ech 'cal Servi es; Level II NDE Technician.
11/83 1/85 13 Universal Testin Labs Inc.; Level II NDE Technician.
1/77 11/83 60 U. S. Steel Co .; Level II NDE Technician, Trainee, and Level I covered during this employment.
CERTIFIED BY TITLE DATE Z 2. 90 REVIEWED BY THIS CERTXFZCATZON ZS VALID UNTXL 2. 2-N SUPERVISOR
<<All historical information supplied by me to compile this is true and correct to the best of my knowledge>>
c rtifica
JNS-QI 9.3 Revision p 0 NONDESTRUCTIVE EXAMINATION PERSONNEL CERTIFICATION NAME CRIS M. REDDING CERTZFZCATZON LEVEL I
ZI EXAMINATION METHOD LI UID PENETRANT LIMITATIONS NONE
-.~PXAMINATZON RESULTS:
BASZC4 ~NA ADMINISTERED BY DATE (METHOD4) GENERAL ~78 ADMINISTERED BY F. T CARR DATE ~12 28 89 SPECIFIC 90% ADMINISTERED BY F. T. CARR DATE ~12 28 89 PRACTICAL ~94 ADMX11ZSTERED BY F. T. CARR DATE 01I108 90 COMPOSITE ~87.3 (AVERAGE OP ALL SCORES) *LEVEL IZZ ONLY EXPERZENCEW (INVERSE CHRONOLOGICAL ORDER)
DATES NO ~ MOB ~ THZS METHOD COMPANY INCLUDE TYPE OP WORK AND NDE IEVEL 10/89 ~FP ; Level II ISZ Technician performing resent Nuclear~Fossil Plant NDE.
2/87 - 10/89 32 EBASCO Services Inc.; Level IZ ISZ Technician performing PSZ & ISI examinations at a variety of assignments.
6/85 - 7/86 13 World Technical Services; Level II NDE Techni ian.
,11/83 - 1/85 13 Universal Testin Labs Inc.; Level IZ NDE Technician.
1/77 - 11/83 66 U. S. Steel Cor .; Level II NDE Technician, Trainee, and Level I covered during this employment.
CERTIFIED BY TITLE DATE REVIEWED BY THIS CERTZPZCATZON ZS VALID UNTZL ~~ /93 NDE SUPERVISOR
~ 4All histor'cal information supplied
~ ~
by me to co ile this tification is true and correct to the best of my knowledge" EXAMINEE
JNS QI 9 ~ 3 Revision +
NONDESTRUCTIVE EXAMINATION PERSONNEL CERTIFICATION NAME CR S M. REDDING CERTIFICATION LEVEL II EXAMINATION METHOD MAGNETIC PARTICLE LIMITATIONS YOKE & PROD TECHNI UES ONLY I
c'XAMINATZON RESULTS9 BASIC* ~N A ADMINISTERED BY DATE (METEOD+) GENERAL ~78 ADMZNZSTERED BY " . T CARR DATE ~12 .2-? 89 SPECZPZC ~88 ADMZNZBTERED BY F. T. CARR DATE-.~12 -22 89 PRACTICAL 1004'DMINZSTERED BY . F. T. CARR DATE. ~01 26 90 COMPOSITE ~88.6 (AVERAGE OP ALL SCORES) 'LEVEL ZII-ONLY--
EXPERIENCE (INVERSE CHRONOLOGICAL ORDER)
DATES NO ~ MOS ~ THIS METHOD COMPANY INCLUDE TYPE OF WORK AND NDE LEVEL 1
0/89 resent
~FP ;
Nuclear~
Level II ISI Technician performing Fossil Plant NDE.
2/87 - 10/89 32 EBASCO Services Inc.; Level IZ ISI Technician performing PSI & ISI examinations at a variety of assignments.
6/85 7/86 13 World Technical Services; Level Technician.
II NDE 11/83 - 1/85 13 Universal Testin Labs I c.; Level II NDE Technician.
1/77 11/83 U. S. Steel Cor .; Level II NDE Technician, Trainee, and Level I covered during this employment.
CERTIFIED BY DATE /3n a REVIEWED BY TMZS CERTIFICATION ZS VALID UNTIL ~> 0 9+
E SUPERVISOR
~ 'All historical information supplied by me to corn ile this c tification is true and correct to the best of my knowledge<~
EXAMINEE
INSPECTION PERSONNEL EYE EXAMINATION n8 CAP FIRST MIOOI.E Lossdon: Wy S P5 LAST Without Glasses With Glasses fB 0 Chart No. J1 Without Glasses With Glasses . 0 Q/sl~s Chart No Snellen Right Eye H OK 0 See Recommendation Right Eye 0 OK gY See Recommendation Left Eye 8 OK 0 See Recommendation Left Eye 0 OK df See Recommendation Both Eyes OK 0 See Recommendation Both Eyes Br DK tB Bee Recommendation Color Blindness ( Ktsihara 0 tsochromatic ) - Write in Number Read 0 9 17 0 25 33 2 10 18 26 34 3 11 19 27 35 4 12 20 28 36 5 13 21 29 37 6 14 22 30 38 7 15 23 31 8 16 24 32 Recommendation.'emarks:
Pass ~see Physician &Restricted Fail QIt/
L ~D lS 4d ZJC~~ ~ ~-2 IS W~
~ I ?
r~>dnJ I Irl/rrp Test Administrator Date Applicant's Signature m Date tO NOTE: THE ABOVE DATA WILL MEET THE SNT-TC-1A/ANSI N46 2.6 REQUIREMENTS LATEST REVISiON.
forest a302 3,2 tNon Stocitoet) Rev 2rs
CERTIFICATION OF PERSONNEL QUALIFICATION TRAI NING SUPPLEMENT SCHOOL (PROGRAM) LOCATION DATE LENGTH SUB JECT Texas /75 G.E.D.
U. S. Steel Baytown, 24 hrs. Magnetic Particle U. S. Steel Baytown, TX 1980 24 hrs. llagnetic Pat ti cue.
U. S. Steel Baytown, TX 1979 40 hrs. Ultrasonics Level I U. S. Steel Baytown, TX 1980 40 hrs. Ultrasonics Level II U. S. Steel Baytown, TX 1978 24 hrs. Liquid Penetrant U. S. Steel Baytown, TX 1979 24 hrs. Liquid Penetrant EPRI NDE Center Charlotte, NC 2/84 40 hrs. UT IGSCC Detection EPRI NDE Center Charlotte, NC 7/88 40 hrs. UT IGSCC Sizing EPRI NDE Center Charlotte, NC 9/88 32 hrs. UT IGSCC Overlay EBASCO Services Kearny, NJ 2/87 pf hrs. Radiation Safety EBASCO Services Kearny, NJ 2/87 $ hrs. Radiography EBASCO Services Kearny, NJ 4/87 Zp hrs. Magnetiw Particle EBASCO Services Kearny, NJ 4/87 5g hrs. Radiography EBASCO Services Kearny, NJ 4/87 16 hrs. Liquid Penetrant EBASCO Services Kearny, NJ 4/87 38 hrs. Ultrasonics AWS EBASCO Services Stuart, FL 6/89 80 hrs. Yisual YT-1 thru 4 FPI Riviera Bch, F 1/90 16 hrs. FPL NDE Procedures
EBASCO SERVICES INCORPORATED EBASCO Materials Engineering Laboratory. Bldg. 100A Port Kearny. South Kearny, NJ 07032. (201) 344-8400 Name: Robbins, Michael D. SSN: 408-94-0001 CERTIFICATION HISTORY Method Basic Method Specific Date itr Level General S~cific Practical Composite 10/05/88 UT-II 87.50 90.00 97.00 92.05 10/05/88 MT-II 90.10 90.00 98.00 93.23 10/05/88 PT-II 76.90 100.0 97.00 91.87 10/05/88 VT-1 II 80.00 100.0 86.00 88.40 10/05/88 VT-3&t II 76.70 95.00 100.0 91.50 09/12/89 VT<<2 II 93.30 95.00 93.00 93.69 e
EBASCO SERVICES INCORPORATE))
CURRENT NDE CERTIFICATIONS NAME: Robbins, Michael D. SSN: 408-94-0001 EDUCATION LEVEL: High School HOURS MONTHS GENERAL/ SPECIFIC/ PRACTICAL/
METHOD LEVEL OF OF DATE BASIC METHOD SPEC-PRACT. COMPOS. RECERT. CERTIFIER TRAIN. EXP ER. CERTIFIED GRADE WT. GRADE WT. GRADE MT. SCORE DUE RT N/A UT II 104 164 10/05/88 87.50 0.3 90.00 0.3 97.00 0.4 92.05 08/04/91 R. PAILLAMAN MT II 24 164 10/05/88 90.10 0.3 90.00 0.3 98.00 0.4 93.23 08/01/91 H. BULLEN PT II 38 164 10/05/88 76.90 0.3 100.0 0.3 97.00 0.4 91.87 08/01/91 H. SULLEN ET N/A VT-1 II 63 132 10/05/88 80.00 0.3 100.0 0.3 86.00 0.4 88.40 08/03/91 R. PAILLAMAN VT-2 II 63 164 09/12/89 93.30 0.3 95.00 0.3 93.00 0.4 93.69 08/22/92 R. Paillaman VT-3,4 II 63 164 10/05/88 76."70 0.3 95.00 0.3 100.0 0.4 91.50 08/03/91 R. PAILLAMAN N/A N/A RESTRICTIONS: NONE ENDOHSEMENTS: ISI This is to certify that the above named person has been found qualified to perform the above listed NDE methods at the levels stated. The individual meets the requirements for education, training and experience as defined in Ebasco Procedure NDE-1, Revision 12, and has successfully completed the required examinations. Individual certification records are on file and available for review at the Ebasco Kearny, New Jersey Office.
I LEVEL III NAME: H.C. Bullen SIGNATURE: DATE ISSUED: 09/12/89
lass U . O'~
R E PORT OF EYE EXAMlNATlON PART - A (To be completed by Eye Examiner)
A NEAR VI ION ACUITY P READ JAEGER J-1 D UNCORRECTED o E A I I ri'r v c IT I S pe i I f I EYEGLASSES y
GYCRft eye 2 ~ 0 CONTACTS
~gt:I e;e
- 8. DISTANT VISION ACUITY P SNELLEN UNCORRECTED OTHER IS peciiyt EYEGLASSES cleft eye )RE g 0 CONTACTS
~igITt eye C. COLOR VISION IS HI HARA 0 OTHER (Specify)
Number of Plates Tested Number of Plates Correctly Read List of Any Plates Read In orrectly NAME OF EXAMINER irrlR 877/ 8 TITLE LOCATION ~~Ar SIGNATURE DATE OF EXAM +P PART - 8 (To be completed by The Appropriate Level III Individual)
MEETS QA ~ G.3.1 JAEGER J-1 Q YES Q NO MEETS QA* G.3.1 SNELLEN MINIMUM ONE EYE20/40 TEE Q NO Q N/A MEETS QA ~ 6.3.1 COLOR VISION Q YES Q NO' N/A DISCIP EL - III DATE PRINT NAMt SIGNATURE MEETS NDE ~ 1 JAEGER J-1 Q YES Q NO MEETS NDE - 1 SNELLEN MINIMUM ONE EYE 20/30 ~YES ~ NO P N/A MEETS NDE ~ 1 COLOR VISION YES Q NO Q N/A DATE PRINT NAMt SICNATURt i
/f failed. j provide usrificarion for waiver of failed condition:
Aprirct' a ~
e Level III s ERE/air EPO CTNI iM ~ MF i iAi i+Nl/ 'tg
EBASCO SERVlCES tNCORPORATED EBASCO Materials Engineering Laboratory, Bldg. 100A Port Kearny. South Kearny. NJ 07032, {201) 344-8400 Name: Kovalovich, Paul SSN: 050-60-7171 CERTIFICATION HISTORY Method Basic Method Specific Date 6 Level General ~Secific Practical Camacsite 10/88 UT-II 92.50 100.0 94.00 95.35 10/88 MT-II 83.40 80.00 93.00 86.20 10/88 PT-II 90.00 90.00 93.00 91.20 10/88 VTl-II 73.40 100.00 80.00 84.02
I I o ~
I o
~ I ~ I I ~ I I II '
lo I RRIRiH 585%RRRR I I o ~
' I II I I m o ~
RRRRRRRRR I 'I ~ ~ ~ I ol II mi I~ o ~
585RR55m I I ol ol II I 'I tl mm ~ ~ ~
RRmiH 555RmM I I II I I ol II grig 5855iH
~ o RIIESiK E555iH o ~
I I I ~ ~ I I ~ ~ I I I ' I ~ ~
~ i II I I I I
~ i I I I ~ ~
' I
~ ~ ~ ~ ~ ~ i I ~
~ ~
'333 5.9 88 EBASCO SERVICES INCORPORATEO REPORT OF EYE EXAMINATlON s A I ti 4 u/gch ohio dd 7i 7/
PART - A (To be completed by Eye Examiner)
A. NEAR VISION ACUITY
~0 READ JAEGER J-1 READ OTHER (Specify) 0 UNCORRECTED EYEGLASSES MLe eye 0 CONTACTS B. DISTANT VISION ACUITY SNELLEN 0 UNCORRECTED 0 OTHER (Specify) EYEGLASSES oo 0 CONTACTS CVAight eye C. COLOR VISION I HIHARA 0 OTHER (Specify)
Number of Plates Tested Number of Plates Correctly Read List of Any Plates Read Incorrectly NAME OF EXAMINER TITLE
/\ A LOCATION rr'I SIGNATURE DATE OF EXAM PART - B (To be completed by The Appropriate Level lll Individual)
MEETS QA - G.3.1 JAEGER J-I Q YES Q NO MEETS QA- G.3.1 SNELLEN MINIMUM ONE EYE20/40 Q YES Q NO Q N/A MEETS QA ~ G.3.1 COLOR VISION Q vEs Q No Q N/A DISCIPLINE LEVEL - III DATE hRINT NAMC SIGNATURE MEETS NDE - I JAEGER J-1 QvEs Q No MEETS NDE ~ I SNELLEN MINIMUM ONE EYE 20/30 Q vEs Q No Q N/A MEETS NDE - 1 COLOR VISION Q vES Q NO' N/A NDE - LEVEL III ~ 'o ci PRINT NAME SIGNATURE
'lffailed. provide justification for waiver of failed condition:
ApprOpriate LeVel III S ghsiuie shd OsI ~
See reverse side lorinsrrIrerlons.
4' I ' '1 0 ' h'0 PP 'r Iir r)Q J \* w PQ T hl'ee fg+0'Th Mc vR ~ 'R 'l0 r Jlr s Pfh ~ $ 4rl 1 i < *v
EBASCO SERVICES INCORPORATED Name: Vano, Richard J SSN: 167-58-4514 CERTIFICATION HISTORY Basic/ Method/ Specific/
Date Method Level General Specific Practical Composite 09/08/89 UT 90.00 85.00 81.00 85.80 09/11/89 PT 93.30 90.00 93.00 92.22 01/18/90 MT 75.00 95.00 92.00 86.10
{<< '. (('IF'<<<< '<<'<<0 +0,( Y <<{ <<<<<< ', '{ l{Y <<"
{ Q$ 'll<<P " <<(( (P'f<<7<< '<<<<{ P ~
e I
~ ~
I e I ~ I I 'I I ~
~ ~
I ' ~ ~
) ~
RRESHR RiE5%R5m I'e ee
'I
' II II 'I 'I m
~ II m I>> I ~ ~
m I I I I e I I I I
' I I I ' >>
RRRi%
~ e Remi%
mmrm mERi%
RE ~ IRiH
~ ~
I
~ e>> I I I I I I I I ~ I ~ I I t
' I i I I i I ~ ' '
~ I
~ ~
' I ~ I I I ~ I I
~ I ~ i ~
i I '
/l; I I
I"33 5 9 88 EBASCO SERVICES INCORPORATED REPORT OF EYE EXAMINATION NAME attJ O PART - A (To be completed by Eye Examiner)
A. NEAR VISION ACUITY El READ JAEGER J-1 Itr UNCORRECTED 0 READ OTHER (Specify) 0 EYEGLASSES IB Left eye
~-1 0 CONTACTS S Right eye B. DISTANT VISION ACUITY EV SNELLEN ~UNCORRECTED 0 OTHER (Specify) 0 EYEGLASSES a;...,. 0 CONTACTS C. COLOR VISION 0 ISHIHARA IEI OTHER (Specify)
Number of Plates Tested Number of Plates Correctly Read List of Any Plates Read Incorrectly NAME OF EXAMINER TITLE LOCATION Sa ~
SIGNATURE DATE OF EXAM PART - B (To be completed by The Appropriate Level ill fndividual)
MEETS QA - G.3.1 JAEG Q YES Q NO MEETS QA- G.3.1 SNELLEN MINIMUM ONE EYE20/40 QYES QNO Q N/A MEETS QA - G,3.1 COLOR VISION Q YES /A DISCIPLINE LEVEL - III DATE PRINT NAME SIGNATURE MEETS NDE - 1 JAEGER J-1 YES Q NO MEETS NDE - 1 SNELLEN MINIMUM ONE EYE 20/30 Q YES Q NO Q N/A MEETS NDE - 1 COLOR VISION ~ES Q NO' N/A NDE. LEVEL. III .. r I
PRINT NAME auMZ SION URE DATE
'll'feiled, providejttstift'cation for waiver of failed condition:
ApprOpriate LeVel III Slpnstllrd end 05I ~
Sdd reverse side lorinstfuctions
EBASCO SERVICES INCORPORATED EBASCO Materials Engineering Laboratory, Bldg. 100A Port Kearny, South Kearny, NJ 07032. (201) 344-8400 Name: Michael Brannin SSN; 141-60-0508 CERTIFICATION HISTORY Method Basic Method Specific Date a Level General ~Seclfic Practical Comcoskte 09/08/89 UT I Trainee 90.00 85.00 83.00 86. 40 09/08/89 PT I Trainee 86.70 85.00 97.00 89. 28
EBASCO SERVICES INCORPORATED CURRENT NDE CERTIFICATIONS NAME: Brannin, Michael P SSN: 141 60 0508 EDUCATION LEVEL: High School HOURS MONTHS GENERAL/ SPECIFIC/ PRACTICAL/
METHOD LEVEL OF OF DATE BASIC METHOD SPEC-PRACT. COMPOS. RECERT. CERTIFIER TRAIN. EXPER. CERTIFIED GRADE MT. GRADE MT. GRADE WT. SCORE DUE RT N/A UT IT 80 0 09/08/89 90.00 0.4 85.00 0.3 83.00 0.3 86.40 08/30/92 R. Paillaman MT N/A PT IT 16 09/08/89 86.70 0.4 85;00 0.3 97.00 0.3 89.28 09/08/92 H.C. Bullen ET N/A VT-1 N/A VT-2 N/A VT-3,4 N/A N/A N/A RESTRICTIONS: NONE ENDORSEMENTS: NONE This is to certify that the above named person has been found qualified to perform the above listed NDE methods at the levels stated. The individual meets the requirements for education, training and experience as defined in Ebasco Procedure NDE-1, Revision 12, and has successfully completed the required examinations. Individual certification records are on file and available for review at the Ebasco Kearny, New Jersey Office.
. LEVEL III NAME: H.C. Bullen SIGNA'ICE: DATE ISSUED'9/11/89
- 33~ 5 9 88 EBASCO SERVICES INCORPORATSO REPORT OF EYE EXAMINATlON g,r> I /- ('.o- oG-c8-PART - A (To be completed by Eye Examiner)
A. NEAR VISION ACUITY Ef READ JAEGER J-1 0)v UNCORRECTED Q READ OTHER (Speci(y) Q EYEGLASSES Itr Left eye ~- l Q CONTACTS B. DISTANT VISION ACUITY
~SNELLEN NCORRECTED Q OTHER (Specify) Q EYEGLASSES 9YCeft eye Q CONTACTS
~tght eye C. COLOR VISION Ef ISHIHARA Q OTHER (Specify)
Number of Plates Tested Number of Plates Correctly Read List of Any Plates Read Incorrectly NAME OF EXAMINER TITLE LOCATION o SIGNATURE DATE OF EXAM PART - B (To be completed by The Appropriate Level ill Individual)
MEETS QA - G,3.1 JAEGER J-1 Q YES Q NO MEETS QA- G.3.1 SNELLEN MINIMUM ONE EYE20/ YES Q NO Q N/A MEETS QA - G.3.1 COLOR VISION Q YES Q NO' N/A INE LEVEL - III DATE PRINT NAME EIQNATURE MEETS NDE - 1 JAEGER J 1
~YES Q NO MEETS NDE. 1 SNELLEN MINIMUM ONE EYE 20/30 ~YES I3 No CI N/A MEETS NDE-1 COLOR VISION YES Q NO Q N/A NDE . LEVEL . III ~f'ds n, rItn~zk. DATE PRINT NAME Sl NATURE
'lffailed, provide justi%'cation for wei ver of feiled condition:
ApprOpriate LeVel III SiOnstwe end Oste See reverse side forinstrtrotrons.
FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO 88-08 APPENDIX C EQUIPMENT CERTZFICATZONS ULTRASONIC EQUIPMENT PRE POST MODEL SERIAL NO OUTAGE OUTAGE NUMBER LINEARITY LINEARITY USL-48 213222 02/05/90 03/23/90 USK-7 27276-1078 02/05/90 04/04/90 USK-7 27276-1091 02/05/90 03/23/90 19 ttf h, h% IVfl1+g 'I'g'@1M'AW'+ *Ill * ' 'KQVLW 4,)We+hCWW)tjt w eke e(PI
pRg -OuTAQE. LINGARIT'(
PROCEDURE CAL-1 ULTRASONIC INSTRUMENT. LINEARITYRECORD INSTRUMENT CALIBRATIONBLOCK
~
Model No. Type . ~rr TRANSDUCER Brand geo%
Frequency 2a 2 Sze aI Straight Beam ( W Brand Frequency Sze Angle Beam ( erf VERTICAL LINEARITY (SIGNAL AMPLITUDES IN % FSH)
HORIZONTAL LINEARITY LOW GAIN ACTUAL (CALCULATE) ACTUAL BACK ,GRID ACCEPT O. HIGHER LOWER REFLECTOR LOC. LIMITS SIGNAL 1/2 OF ACCEPT. SIGNAL HIGHER LIMITSB l ) l +).( 5) 1.90 - 2.10 l S) l )~ ( 4( )
2.85 3.15 HO) l LI5)( )
3.80 -4.20 I l I 4(O ).( )
4.75 ~ 5.25 ( 90) ( 35 ) I Z5 )
5.70 .8.30 (ZS) (~) l ~
ZO )
6.65 - 7.35 ZCg l (Z5) I )5)~
7.60 ~ 8.40 l I ) (Za) I )O)~
8.55 ~ 9.46 (]0 l I lg ).l 10 10 10 10 IO ( 5 l (IO) ( 0 ~ )
'Acceptance Limits are 1/2 of the Higher Signal k 5% FSH AMPLITUDE CONTROL LINEARITY
~
LOW GAIN HIGH GAIN INITIAL db ACTUAL (CALCULATE) ACTUAL AMPU1UOE CHANGE RESULT I.IMIT HIGHER ACCEPT. LOWER AIQNAL 112 OF SIGNAL
&0% FSH DOWN 6 32% ~ 48% HIGHER LIMITSB 80% FSH DOWN 12 16% ~ 24% )OO l I l55) ( ~ )
40% FSH UP 6 5) I ).( (/O) 20% FSH UP 12 I 5)( 3S )
HIGH GAIN 5 INITIAL db PLfAAK CHANGE RESULT LIMIT le)
I l 25)
)
I (35)l
~)
)~ (
~ ( ZO)
)
5 l 80% FSH DOWN 6 32% 48% I ZO) I Z )-I I 80% FSH DOWN 12 18% - 24% (/S l l ZO).( )0 I 40% FSH UP 6 64% ~ 96% l /O) ( /5) I ((B )
20% FSH UP 12 61%.96% 10 ( ) I ).I 0 )
sAcceptance Limits are 1/2 of the Higher Signa) k 5% FSH Performed By:
UT Level: Oete: Z $'0
~
r>>>>h r, W,, ~ e' r r>> ' ', >> '>>r r<<n>> t>>rt gr Vg'>>y>>. >> ne>>tt "rr>>>>
Form 3327 (Non stockeo) Roy. Lilt(6
~" art tt Z'rrr +'(re gr Y'4
PROCEDURE CAL-1 ULTRASONIC INSTRUMENT LINEARITYRECORO INSTRUMENT CALIBRATIONBLOCK Model No. V Serial No.
TRANSDUCER Brand Brand K Frequency Frequency Size Q~ Angle Beam ( )
VERTICAL LINEARITY (SIGNAL AMPLITUDES IN '%SH)
HOB I2ONTAL LINEARITY LOW GAIN ACTUAL (CALCULATE) ACTUAL BACK GRIO ACCKPT O. HIGHER LOWER REFLECTOR LOC. UMITS SIGNAL 1/2 OF ACCKPT. SIGNAL HIGHER LIMITS~
1.90 ~ 2.10 I
)
)
I I - )I ygya)
~ I
)
2.85 ~ 3.15 I ) ( ) I ~ )
3.80 -4.20 I -) I )~ (3o) 4.75 5.25 l3o) I )~ li+)
l~~)
5.7o e.3o I y ) I )~
8.65-7A O) /
0 I I )~ I )
7.60 8.40
~ I/S ) I )~ I jg) 8.55 ~ 9 45 )~I )
10 10 10 10 I ) I ) I )
'Acceptance Limits are 1/2 of the Higher Signal + 5% FSH AMPLITUDECONTROL LINEARITY HIGH GAIN LOW GAIN INITIAL dh ACTUAL (CALCULATE) ACTUAL AMPLIATE)E CHANGE RESULT LIMIT LOWER O. HIGHER AIGNAL 1/2 OF ACCEPT. SIGNAL 80% FSH DOWN 6 32% 48%
~ HIGHER LIMITS~
80% FSH DOWN 12 16% ~ 24% I g ) I~ )~ I 40% FSH Upe 84% 96%
~ I ~) I )I gQ) 20% FSH UP 12 64% ~ 96% I ) I -)I+ )
HIGH GAIN 0 I 3 ) I )I O )
INITIAL db I ) I )~ I )
RESULT LIMIT PLIILNE CHANGE ~ lgg) I 80% FSH OOWN d 32% ~ 48%
I I >0)
)
Ia
~
)~ I /") )
80% FSH OOWN 12 16% ~ 24% I I I )~ I )
40% FSH UP 8 I ) I /5-) ~ I )
20% FSH UP 12 64%. 98% 10 I ) I/O) I ~
0 )
'Acceptance Limits are 1/2 of the Higher Signal i 5% FSH Performed By:
UT Level: Date:
s/
I'r>> - >>~<~>> L i ~ >>c ~ L t~/ t 4 PROCEDURE CAL.t ULTRASONIC INSTRUMENT.LINEARITYRECORD INSTRUMENT CALIBRATIONBLOCK TRANSDUCER r/
Brand Frequency ;*
Brand Frequency VERTICAL LINEARITY (SIGNAL AlNPLITUOES IN % FSHl
.o'ORIZONTAL LINEARITY LOW GAIN ACTUAL (CALCULATE) ACTUAL BACK GRID ACCEPT O. HIGHER LOWER REFLECTOR LOC. UMITS SIGNAL 1/2 OF ACCEPT. SIGNAL HIGHER LIMITS>>
l 5 ) l ~ I )
1.90 ~ 2.10 l 4 ) l )~ ( )
3 2.85 ~ 3.15 I ) l(/ )I )
3.80 - 4.20 70 l ) l Q>>7 )~ ( )
4.75 - 5.25 ) l3 )l )
5.70 8.30 l ) l )~ l )
8.65 - 7.35 lg ) (P>)-l / )
7.60 - 8.40 I ) (~Q) l ~ )
8.55 - 9.45 l ) ~ I )
10 10 10 ) l/(3)l g )
Acceptance Limits are 1/2 of the Higher Signai R 5% FSH AMPLITUOE CONTROL LINEARITY LOW GAIN HIGH GAIN INITIAL Ewe RESULT LIMIT ACTUAL (CALCULATE) ACTUAL AMPUltÃ7& CHANG& O. HIGHER LOWER AIGNAL 1/2 OF ACCEPT. SIGNAL LIMITS>>
80% FSH 80% FSH 40% FSH OOWN 8 OOWN 12 UP 5 32% ~ 48%
18% ~ 24%
64% ~ 95%
t~)
HIGHER I >>tran-)
(
I
.l
)~ I
+
y) 20% FSH UP 12 54% ~ 95% D) I ~) ~ I HIGH GAIN I ) I+Q) I ~ )
INITIAL PLALXX CHANGE RESULT LIMIT 0) I )~ lg )
(3 ) IRO )
80% FSH OOWN 5 32% ~ 48% ) ( > rr ) ( /
~ )
80% FSH DOWN 12 16% ~ 24% 3o / ) I l9) ~ I /g )
40% FSH UP5 64% ~ 96% I ) I/ )I )
20% FSH UP 12 54% 95% 10 I ) I/ )I )
>>Acceptance Limits are 1/2 of the Higher Signal R 5% FSH Performed By:
UT Level: Date: Z-~ O Form 3327 (Non stock>>4) Aev. 13/sr
pB5 /
ULTRASONIC INSTRUMENT O)@e Lr'~urgrr LINEARITY
$ RECORD PROCEDURE CAL-1 INSTRUMENT CALIBRATIONBLOCK Model No Serial No. cg) 7 +~ /~71 Type 5 Serial No.
TRANSDUCER Brand Brand Frequency 5 ~rI + Bite Size
~Z J(J~
Ig straight Beam Angle Beam
(~
t )
VERTICAL LINEARITY (SIGNAL AMPLITUDES tN % FSH)
HORIZONTAL LINEARITY LOW GAIN (CALCULATE) ACTUAL BACIC GRID, ACCEPT NO.
ACTUAL'IGHER LOWER REFLECTOR LOC. LIMITS SIGNAL 1/2 OF ACCEPT. SIGNAL HIGHER I.IMITS' 5'0 ) l AI )~ ( )
1.90 - 2.10 ) l
( )~( O )
2.85 ~ 3.15 ( ) ( 5 )~ ( g )
3.80 - 4.20 l ) ( )~ ( )
4.75 - 5.25 l ) )~( )
(~)
(
5.70 - 6.30 t ) ~
l )
6.65 - 7.35 l ) (/ )~ ( )
7.60 - 8.40 ( ) l' ~
( )
8.55 ~ 9.45 (/g ) ( ) (
~ )
10 10 10 10 <<o ).(/o
'Acceptance Limits are 1/2 of the Higher Signai + 5% FSH AMPLITUDECONTROL LINEARITY LOW GAIN ~ HIGH GAIN INITIAL db ACTUAL (CALCULATE) ACTUAL AMPUTUOE CHANGE RESULT LIMIT O. HIGHER LOWER AIGNAL 1/2 OF ACCEPT. SIGI(IAL 80% FSH DOWN 6 32% ~ 48% HIGHER LI MITS B 80% FSH DOWN 12 16% - 24% (5'0 ) I 5 ).(rb ) 0 40% FSH UP 6 64% ~ 96% I%5') l )l 0 )
20% FSH UP 12 64% - 96% D ) l35-)-(e5- ) tO HI GH GAIN l ) (30 ).(A/0 )
INITIAL db RESULT LIMIT 0 ) (>K)-(~s ) 3 AMPLITUDE CHANGE
( a5 ) (ao).(ao 80% FSH DOWN 6 32% ~ 48% l ) l/AA )l )
80% FSH DOWN 12 16% ~ 24% / ) l /g ).((iL(F) ) /
40% FSH UP 6 64% - 96% I /0 ) l &).(/f ) JO 20% FSH UP 12 64%-96% 10 ) (O )(/0 )
'Acceptance Limits are 1/2 of the Higher Signal + 5% FSH Performed By:
UT Level: De,e: V-+-98
,. t
', l~
r ne e m e rahu . ~ 'ety ~n eeeemeu n r net r'r ee Ir'" cere . ( ~ ne e~ e n a )puce
PROCEDURE CAL-5 ULTRASONIC INSTRUMENT.LINEARITYRECORD INSTRUMENT CALIBRATIONBLOCK Model No.
TRANSDUCER Brand -AEko Brand K VERTICAL LINEARITY (SIGNAL AMPLITUDES IN % FSHl HORI2ONTAL LINEARITY LOW GAIN ACTUAL (CALCULATEl ACTUAL BACK GRID ACCEPT O. HIGHER LOWER REFLECTOR LOC. UMITS SIGNAL 1/2 OF ACCEPT. SIGNAl.
HIGHER LIMITS~
( I l )~ l 5l 1.90 ~ 2.10 l ) l )~ l l 2.85 ~ 3.15 o) l 5)( 5) 3.80-4% l ) o) 4.15-52$ I l ll 2 )
~ (3O)(
)
5.10 ~ 0.30 ) ZO) 0.05 -1.3S (ze ) (~) ~ l )5 l 1.50 ~ 8 40 I 5 I ( )~ l I~ l I B.SS - 9.45 20 I /Q ) l (5)( l J 10 10 10 10 10 I 5 l ( IO )( O ) 5
'Acceptance Limits are 1/2 of the Higher Signai k 5% FSH AMPLITUDECONTROL LINEARITY HIGH GAIN LOW GAIN INITIAL db ACTUAL (CAl.CU LATE) ACTUAL.
AMPUTLX)8 CHANGE RESULT LIMIT LOWER HIGHER 1/2OF ACCEPT.
AlGNAL LIMITS~ SIGNAL 80% FSH DowN 0 32% ~ 48% HIGHER 80% FSH DOWN 12 ZO 10% ~ 24% / 0 l l I 5)l )
40% FSH Upe ) l5O) l ~
0) 20% FSH UP 12 I ) I g)l l HIGH GAIN I S) I O) ~ ( 3Q)
INITIAL db LlMIT I ) (35) l 45)
~
30 FLrlta)E CHANGE ( 25) Z5 80% FSH DOWN 0 32% ~ 48% I ) (25) ~ I I5) 80% FSH DOWN 12 10% 24% l5 I l ZO) ~ ( IO) 15 40% FSH ur e 54% -90% I /0 I ll5)l IO 20% FSH UP 12 04% 90% 10 IO I S ) (IO)(
~Acceptance Limits are 0/2 of the Higher Signal k 5% FSH Performed By:
UT Level: Date:
PROCEOURE CAL-1 UI.TRASONIC INSTRUMENT.LINEARITYRECORD INSTRUMENT CALIBRATIONBLOCK M 5K.-7 z Model No. Serial No.
TRANSDUCER Brand Frequency Size -S 6 Straight Beam Brand Frequency Size ~zr Angle Beam i i VERTICAL LINEARITY (SIGNAL AMPLITUDES IN % FSH)
HORIZONTAL LINEARITY LOW GAIN ACTUAL (CALCULATE) ACTUAL BACK QRI 0 ACCEPT NO. HIGHER LOWER REFLECTOR LOC. UMITS SIGNAL 1/2 OF ACCEPT. SIGNAL HIGHER 1.90 - 2.10 l~o I /~
)
)
(~
I LIMITS o
)~ I
)~ l
~)
y )
2.86 ~ 3.16 l ) )~ (g-)
3.80 ~ 4.20 l ) I dPo) I
~ )
4.7S ~ 52S l 3Q) )-l -)
5.70 ~ 8.30 (~ ) (go) (~g
~ )
e.es.7.35 l ) )-l I er- )
7.60 ~ 8.40 l ) (gg) ~l
/0 )
8.55 ~ 9.45 l g ) (c ).I 3 ) /c) 10 10 10 10 I g- ) (gg) I 0
~ I
~Acceptance Limits are 1/2 of the Higher Signal + 5% FSH AMPLITUDE CONTROL LINEARITY LOW GAIN HIGH GAIN INITIAL db RESULT LIMIT ACTUAL (CALCULATE) ACTUAL AMPUTLX)E CHANGE O. HIGHER LOWER AIGNAL 1/2 OF ACCEPT. SIGNAL 80% FSH oowN e 32% ~ 48% HIGHER LIMITSo 80% FSH OOWN 12 16% - 24% I ~~ ) LI~) l y~)
~
40% FSH UP 6 64% - 95% l (~cg )-I
~)
)
20% FSH UP 12 54% ~ 96% l err~ ) l 4r~).(
Hl GH GAIN I ) (ego) I~
3o)
INITIAL. dIB RESULT LIMIT l > ) l 3~.( Ay-)
PLAlKE CHANGE ~) l 3o).l ~ ~)
80% FSH oowN 6 32% ~ 48% l /O) (4 )I / )
80% FSH OOWN 12 16% ~ 24% l iS-) (Ao) l ~
/D) 40% FSH UPS 64% ~ 98% l i ) (igr) l
~
~ )
20% FSH UP 12 81% 96% 10 l ) (/g )l D )
BAcceptance Limits are 1/2 of the Higher Signal + 5% FSH Performed By: P'P~
UT Level: Dete 3- ~3- 0 au ~ 3/z3/8
I t
'I I
s ~
'I 4
J
'k C
I' I
~'
t ~ l7, F7'( t h 7
FINAL REPORT OP INSERVZCE INSPECTION NONDESTRUCTZVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO+ 88-08 APPENDIX D EQUIPMENT CERTZPZCATIONS ULTRASONIC SEARCH UNZTS SERIAL NO TYPE SIZE FREQUENCY D24473 GAMMA MSWS ~ 25" 2. 25 H12310 GAMMA MSWS 25fl 2 ~ 25 L23777 GAMMA MSWS ~ 25" 2 '5 20'
TRhHSDUCER CERTIFIChTIOH
\
~nsducer Descri Fr@ agency tion s/s MHs Sise ~~
a TRJLCC Contact Immersion Honfocused Z Water Path Spherical rget J Cylindrical TRhCK IZ L itive Sensitivity dB Energy Setting ~~ Impedance ~~jQ TRhCK IIZ Peak or Center Frequency . MHs 1
Inspector Date 9-C D Testin Procedure The real time waveform shown in the photo above is the first return echo from a reflector
'ducted with respect to transducer type. hll contact (wearplate) transducers are tested a steel (4340) plate Wile epoxy-faced shear wave transducers are teste4 on a flat po Dual contact transducers are, tested on a flat polymer block unless otherwise specxfied. Delay fingertip removable (Style DFR) transducers are tested off of the tip of the delay line. Monfocused immersion transducers are tested in wator over a flat steel plate using a water path as specified above. Focused &aversion transducers are tested the same as noniocused transducers except that tho water path used is equal to the actual focal length.
Using an hEROTECH Ultrasonic Transducer hnalyser, Model UTh-4, and a Tektronix 7L12 frequency spectrum analycer in a 7704k Mainframe, the real time waveform, UTh;4 gate signal, and the frequency spectrum of the gated signal are simultaneously displayed and photographed.
Using the linear attenuator in the UTh-4 receiver, tho amplitude of the real time waveform is adjusted to a six centimeter amplitude (+ 1 dB) on the CRT. Qith the vertical calibration of ace II fixed at 100 millivolts por division, tho amount of attenuation used provides a
@tive sensitivity rating for a11 transducers certified by Xcautkramer Branson.
Real Time Wavaform -. Trace IZ I
Screen writing figures h an4 F provide the vertical an4 horizontal screen calibration respectively for Trace II.
Cate Marker ~ Trace I Screen writing figure C provides the vertical amplitude of the gate marker an4 is anTrace inconsequential figure. Tho horisontal calibration for Traco I is the same as that for II. Me portion of Trace II that falls within the gate time period is tho signal fed to the frequency spectrum analyser.
e uenc S ect Trace IIZ Screen writing figure K provides the horisontal calibration for Trace III. Figures 4 J the spectrum analyzer s attenuator and resolution settings respectively.
XMUTKRhMER BRhHSOM P 0. Box 350 Lovistown, Ph 17044
Transducer Description ries C TRACE MHz Size~5'o.
~ Contact ~ Water Immersion ~ Nonf ocused Path ~ Spherical
~ Cylindrical Style u.~ Connector ~) TRACE II Re1ative Sensitivity OB %MS>
gy Setting~~ Impedance SQ.rt.
TRACE NL'RNRRRKNS Inspector ( Date Testin Procedure C D E The real time waveform shown in the photo above is the first return echo from a reflector selected with respect to transducer type. All contact (wearplate) transducers are tested on a 1.0" flat steel (4340) plate while epoxy-faced shear wave transducers are tested on a flat polymer block. Delay fingertip removable (Style DFR) transducers are tested off of the tip of the
~ lay line. Nonfocused immersion tr ansducers are tested in water over a flat e 1 plate using a water path as specified above. Focused immersion saucers are tested the same as nonfocused transducers except that the path used is equal to the actual focal length.
Using an AEROTECH Ultrasonic Transducer Analyzer, Model UTA-4, and a Tektronix 7L12 frequency spectrum analyzer in a 7704A Mainframe, the real time waveform, UTA-4 gate signal, and the frequency spectrum of the gated signal are simultaneously displayed and photographed. Using the linear attenuator in the UTA-4 receiver, the amplitude of the real time waveform is adjusted to a six centimeter amplitude (+ 1 db) on the CRT. With the vertical calibration of trace II fixed at 100 millivolts per division, the amount of attenutation used provides a relative sensitivity rating for all transducers certified by
".autkramer Br anson.
Real Time Waveform - Trace II Screen writing figures A and F provide the vertical and horizontal screen calibration respectively for trace II.
Gate Marker - Trace I Screen writing figure C provides the vertical amplitude of the gate marker and is an inconsequential figure. The horizontal calibration for trace I is the same as that for trace II. .The portion of trace II that falls within the
".te time period is the signal fed to the frequency spectrum analyzer.
'ency ~S ectrum - Trace III reen writing figure E provides the horizontal calibration for trace III.
< I> res B and 0 show the spectrum analyzer's attenuator and resolution settings respectively.
KRAUTKRAMER BRANSON e ~ - .~s = ' m'a . r ~ t h he" P. 0. Box 350
~ ' r 'f'h t *el . h Ip pevT '* m + sag @lorn a '
YK i 't hs~
TRANSDUCER CERTIFICATION Transducer Descri tion es SiN B Prequency .-
~ HHS Sita ~~
TRACE Contact Immersion Nonfocused I Pv5%Ãi'%RR~iiig Spherical 5IRWlww r~
Target .6 y < +Cylindrical TRACE ative Sensitivity ~ dB IX Energy Setting M Impedance ~~ TRACE IIX peak or QCenteo Ptequency e2 3. HHa Inspector Date C D Testin Procedure The real time waveform shown in the photo above is the first return echo from a reflector
'.ected with respect to transducer type. All contact (wearplate) transducers are tested on a
. steel (4340) plate while epoxy-faced shear wave transducers are tested on a flat p
- k. Dual contact transducers are tested on a flat polymer block unless otherwise specified. Delay fingertip removable (Style DFR) transducers are tested off of the tip o. the delay line. Nonfocused immersion transducers are tested in water over a flat steel plate using a water path as specified above. Focused immersion transducers are tested the same as nonfocused transducers except that the water path used is equal to the actual focal length.
Using an AEROTECH Ultrasonic Transducer Analyzer, Model UTA-4, and a Tektronix 7L12 frequency spectrum analyzer in a 7704A Mainframe, the real time waveform, UTA-4 gate signal, and the frequency spectrum of the gated signal are simultaneously displayed and photographed.
Using the linear attenuator in the UTA-4 receiver, the amplitude of the real time waveform is adjusted to a six centimeter amplitude (+ 1 dB) on the CRT. With the vertical calibration of
>-ace ZZ fixed at 100 millivolts per division, the amount of attenuation used provides a ative sensitivity rating for all transducers certified by Krautkramer Branson.
Real Time Waveform Trace IX Screen writing figures A and F provide the vertical and horizontal screen calibration respectively for*'Trace IX.
Cate Marker Trace I Screen writing figure C provides the vertical amplitude of the gate marker and is an inconsequential figure. The horizontal calibration for Trace I is the same as that Eor Trace II. The portion of Trace IZ that falls within the gate time period is the signal fed to the frequency spectrum analyzere uenc S ectrum Trace IIZ Screen writing figure E provides the horizontal calibration for Trace IIZ. Figures d
..ow the spectrum analyzer's attenuator and resolution settings respectively.
KB@ggKRAMER BRANSON P. 0. Box 350 Lewistown, PA 17044
FINAL REPORT OP ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX E EQUIPMENT CERTZPZCATIONS ULTRASONIC COUPLANT BATCH MANUFACTURER DESCRIPTION NUMBER 8330 ECHO LABS ULTRAGEL II 21
~,* *,v v'\" t 'g$ *.
8RANCH OFFICES Cable Addrotst INTEL Chloooo, illinois Phliodoiphlo. Ponnsylconlo Intarnalianal '",e ass O aralarios, Ina r Telest I]9187 gatrriaA 2 .tg'g>a '
'ng Znp'nosed Wflighars, 'Pgm ply si' Assayers 578e58,6~ STREET NEWAR e ~ J. oytos
~
rsHOHco 42011 So~772~
No. 486170 DATE February 4, 198 Oar assay of the salrtple of Ultragel II Technicare-Echo, Incoprorated Marked: Batch IiI8330 Spec. AS'-D-129 and ASTM-D-808, 1982 Purchase Order No. 008647 SIN aad submitted to sh<
Halogens (Chlorides): 21.4 ppm Sulphur 4.9 ppm I, David A. Hoffman, Director of Laboratories, do hereby certii';
that the above is true arid correct.
Sworn to and Subscribed befor me this 4ta day of Feb~;ry- 1983.
( r'~e ~7~~.
i>ly Nojary&Gblic Cos"efssioo e iree To Autos't 13, 1984.
Technicare-Echo, Incorporated Lewistown, Penna. INTERNATIONALTESTING LABORATORIES, I Y Thc liability of tire International Testine Laboratories, lnc. with rcspccc to thc duracd for hcrcioe dull ht oo ascot cacccd the amount of the incoicc.
Oor reports pcrtshs to che sample coated only. Ioformacioo contained hcrcin ia ooc to be reproduced, escape with ooc pcstoiaaioo. IT@ 4 Iso ncv. sore 2 ea I ' *Msgr 4 \ Y +pl ~ wr 9'es esu tlirt ~ sos ~, s e, e 'p + 4'L, I t w"e'o~ ply
FINAL REPORT OP ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRBSS BPPECTS REFERENCE NRC BULLETIN NO ~ 88 08 APPENDIX P EQUIPMENT CBRTZPZCATZONS SURFACE THERMOMETBRS SERIAL MANUFACTURER CAL DATE EXPIRATION NUMBER DATE 90-006 PTC INSTRUMENTS MODEL 312F 01/19/90 04/19/90 90-010 PTC INSTRUMENTS MODEL 312F 01/19/90 04/19/90 22
~ WS i- ~,, I t, ~,.] ~, y, 4 4 ~ ~ qe0 ',I r V ~ lp ~
~ ~ ~, ~ 0, ), ~,
(
1 ~ ~ >>i p a't 0 . ".' ".p, tNIV fV %%i I 0 %%~ttq'f ~ ~ r
TEMPERATURE INDICATOR CHECK RECORD (S/N)Identification CHECK READINGS 50o F CHECK VOID HIGH DATE DATE STD. METER STD. METER SIGNATURE
-/ d q@0 STRU T ONS:
(1) Place your indicator and the control indicator side by side in a cold location (or in contact with a cold item). Wait 60 seconds or until the readings stabilize, whichever is longer.
(2) Read and record the readings from both.
(3) Place the two (2) indicatoxs in a fairly warm area (50 F hotter) or in contact with a hot item. Bait 60 seconds or until the readings stabilize, which-evex's longer.
(4) Read and record the readings from both.
(5) The respective readings shall agree within + 104 (6) Retain a copy for your records, forward original to the Juno file.
Reference (Control Unit) Standard Identification (S/N)
Reference (Control Unit) Standard Calibration Date t ~' 1 q ~
TEMPERATURE INDICATOR CHECK RECORD (S/N) Identification CHECK READINGS 50o F CHECK VOID HIGH DATE DATE STD, METER STD. METER SIGNATURE S RU ON (1) Place your indicator and the control indicator side by side in a cold location (or in contact with a cold item). Mait 60 seconds or until the readings stabilize, whichever is longer.
(2) Read and record the readings from both.
(3) Place the two (2) indicators in a fairly warm area (50O F hotter) or in contact with a hot item. Mait 60 seconds or until the readings stabilize, which-ever is longer.
(4) Read and record the readings from both.
(5) The respective readings shall agree within + 104 (6) Retain a copy for your records, forward original to the Juno file.
Reference (Control Unit) Standard Identification (S/N)
Reference (Control Unit) Standard Calibration Date
~W t - 's '
~ '" '7
~
' ph qh, APpp,a~q',(, ryrvyf *rahu 'I, w,O' 'gl, fggl )1 'thp eC itpge%
FINAL REPORT OP ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO 88-08 APPENDIX 6 EQUIPMENT CERTZFZCATZONS PENETRANT MATERIAL BATCH NO. MANUFACTURER TYPE DESCRIPTION 89K039 MAGNAFLUX SKL-HF/S SPOTCHECK PENETRANT 87M02S MAGNAFLUX SKC-NF/2C-7B SPOTCHECK CLEANER 88B019 MAGNAFLUX SKD-NF/ZB-9B SPOTCHECK/ZYGLO DEVELOPER 23
Date; October 25 1989 Purchase Order No. C90663 901
~ ,~BCT: Spotcheck Penetrant Type: SKL-HF/S Batch No. 89K039 We hereby certify that when tasted at the time of manufacture, the above material:
c . Meets the requirements of and has been tested for sulfur and halogens according to:
(a) ASMB Boiler and Pressure Vessel Code, 1983 Edition,Section V, Nondestructive Examination, including all Addenda through Winter 1983 Addendum, Paragraph T-625 and Article 24 as applicable, (b) ASME Boiler and Pressure Vessel Code, 1986 Bdition,Section V, Nondestructive Bxamination, Paragraph T-625 and Article 24 as applicable.
(c) ASME Boiler and Pressure Vessel Code 1989 Edition,Section V, Nondestructive Examination, Paragraph T-625 and Article 24 as- applicable.
(d) AS'-165-80, Paragraph g,l.
(e) NAVSEA 250-1500-1 (Rev. 10 June 1979 and Rev.
12 ~ 5o 1+1.1.
Il May 1983)'Paragraphs 12,5.1.1 and
~
(f) HIL-STD-271F(SH), 27 June 1986, Paragraphs 5.3 and 5.3.1.
(g) MIL-STD-2132A(SH) ~ 15 March 1985, Paragraphs 7.1.1, 7.1.2, and 7.1.3 and Appendix C, Paragraph 30 '
he following test results were obtained:
Sulfur: 0139 wt. 8 of residue. Halogen: 0 0156 wt. 8 of residue Cleaner residue (see Nota 3) Ig/100g, NA g/100 ml
- 2. We further certify that this material does not contain mercury as a basic element, and no mercury bearing equipment was used in its manufacture.
XAGNhP LUX amoott - anager, ua ty ssurance NOTES: 1. Our batch number appears on the bottom of all aerosol cans and on the label of all bulk containers.
2 Most specifications require test results stated in percent but some require
~
parts per million (ppm). To convert "percent" figures to "parts per million" move the decimal four places to the right.
NAVSEA 250-1500-1, MIL-STD-271, MIL-STD-2132, and ASME Section V all require that materials be subject to a procedure to evaporate off volatile solvents before analysis for sulfur and halogen. According to these specifications, only those residues higher than 0.005 g/100 ml shall be analyzed for sulfur an halogen. Lower residues shall be reported.
- 4. The above certification gives the results obtained at the time of manufacture.
Age and use may alter the properties of any material.
R 80-P/( PAGE OF '7 MAGNAFLUx.Ab~is~onot tthnos Toot Wnts tnc ..'F 306lndustriat Stteet I PO Box 366 i, QeWilt lttwa fiPLA9,.$. To>onbnno m No ~ 1/69 R 8/89 qtaMaA>aw,l...ie;11ARCA07t3 ...
,0,40450 ~gj.gip Pt'4'.:<<<<Ills "<< ll<<k c r r R n.vegy:, IYc HF/ c B
.:--"Ho herab certify Chat'hen,tested at the tine cf nanufscture 'he abase asterlal :.', - '~~4
~-,n< Ho herabl '.
ig;,. L;~usets.cherrequlrsaents af sn4 hss been tested for'sulfur snd halog s
~i~(s}~p ASHS loller sn4 pressure vessel code, 1955 gdltlan, ssctloa vy vsndsstfuctlse,~ @j'""',-" '<<, <<
s
$ . ,r,; ~ gssulnstlon, la<<ludlng sll Addenda throui h winter 1955 A44sad~, psrsgra h .T 4 d,~ ';g(bgASHS'eller'n4 pressure vessel cole, 191$ Idltlon,'ect(on,vy'lseadsscructlre '.~
")~+"...-;Wfasn(norton, Paragraph T.e15 snd,Article,la.as sppllcsbleo--"...4-...'~;... ~,.'
'; ~~.-'~J" (C]>',ASTH golag ~ CO, paragraph r.l. ~ - '. .; " ">>;~4 - ." "<~(g)~hOT Standard $ 5 ~ OT. vay LSTC'sn4 October llTS LncludlngQtndssncs. L (1 4'l4):sa4 ='~,' ..
'.<<C(h)saaoensraL'}eccrtc P.S. $ 000;,grr. g ( .TL ~ $ 0) PsrsgtsPhs".'2:5 snd:Tft."',l '~..",
~ ': 'i.:-'"~-- .. r
~.,T b '.',Tine"fsL}suing t ~ st results uere obsolesce.,
.-'-~<<I<<<< ~.,w<<<.<<<<<<n: ~ o'<<i,i<<~aors~ III<<".','.,'..,.'..5!-:..::~
~ . -.i~?.(uelturchor certlfyithat this,notarial'loss not c<<stale nercury.ss ~ .basic elsaent
" - =':i;-"-."i
- z. ~
".~i .~~ao'.sercury'earing'.etulpasnt'uas uss4 la lcs nsnrfsct re, r,; . ~
fv
" '+~', 'I~(v ~ PLaaeoccLL; ~;Oualscy conceal chealst ':, '
'L'. Our batch nuaber a pp sara ~ n t he boston of ~ ll,spray containers and aa Che
- <<agpsLL ether centalnets ~
+~5!4'.",; '
Labe}1);q>>'";g,Skeet speclflcatlens regulre test results stated la pe!coat but'soae reculre ,"<<s~< r sat'u)parce per ullllon (PPH1 ~ To consort "percent" flgerea to "porta.per nCLLLon"'!,"':.c$
t>jaeee tno 4eclasl four places co Ch>> rlsht
,Ss vAVSSA'550 1500.1, Vlh STO ltl, VIL ST5.li}T, aor Ps $ T snd ASVS"Settles V aLL,", ";.'>>
~
~~+.5 that oaterlsls i>> sub}ect co ~ procedure te ees rate aff olatlle 'eculro aoleents before analysis fsr s~lf~r and hslssen, Actor}la to ches y'%'"~
spectflcacleaos only chose resldueo'tgheri 14n Secgg glt04 g Shall bo aaalptad 4> 'r e
fer,sulfur 'an4 halogen+ Cesar tet!dues shall bs reported ga ~ .uae nay ~ LCOr 1 ~ propert(So af any aaCerlsl 6 ~v . ' 't, Tho'abase certlflcstl ~ Siren the reeulC ~ a>>Coined at the tine Ot eanufasturei.n';.(';,'W'!0
'l>ff. 1J <<<<>p)O(V
Date: October 25, .1989 Purchase Order/Contract No. C90663 90169 We hereby certify that the Spotcheck Penetrant, Type SKL-HF/S Batch Nio 89K039 supplied meets the. requirements of VaIL-I-25135E, and is approved by the U.S. Air Force.
When tested according to paragraph 4.4.1.2., Sampling Plan A, the following results were obtained:
t (a) Flash Point (PMCT), 4.5.3 209 OF (b) Viscas1ty~( 5 n'4 ns NominaB, 4.5.4 3 00 cs 4 100oF (c) Developer Fluorescence, 4.5.14 NA (d) Water Content, 4.5.2I NA (e) Penetrant Removability, 4.5.1f ( ~ Standard) Passes (f) Wa ter Tolerance, 4.5.12 NA (g) Fluorescent Brightness of Penetrants, 4.5.7 ( Standard) NA (h) Surface Netting, 4.5.6 Passes (i) Thermal Stability, 4.5.9 NA (J) Redispersibili ty, 4.5.13 NA (k) Valve Leakage, 4e5.20 NA (I) Net Content, 4.5.19 NA
>Ue further certifgj that this material meets the requirements of 51IL-STD-6866 (29 November 1985), Paragraph 4.4.1 and where applicable, 5.8.4.
NAG NAF LUX
~I.J. Plamoottil - .'tanager, Quality Assurance
."-c."m No. 15. 9B
.""..': l0.-'"9 " BO O)fib)'AaE rr fata.f-no.f)(ldll.
MAGNAFt.UX,A On))S)On Ot ttttnOrS TOOt VIOrkS Inc
.306!gdusLftaJ street J @U3ox 36r5.l,.nPw>tt tnwn59gdg rl .Totonttnno t.(-nv;ago.t-(o.ann,
htay¹NASLIIX Carydtafsnn )300 tVttt La+Ftntt AFO>>VO'Ce>>CSQO. CL 60050F'Teepe¹ene 313047009)
\self y>>F'hase Order No.
sel/lcf:-F" "..ec¹/ >.'.o ceoelo eerr,: ".'n >,F/ ¹ Fbi' l .~igB I ve hereby certlty that >>hen tested st tho tine et uaavtactvr". tho above ostarl ~ Li I, Vesta the restulreaentt Ot Snd haa bren teated ter Su)Cur ¹n4 halOgena aCCOF4lng tOC
( ~ ) Asng toiler snd pressure vest ~ I cede, 151) !dition, !ection v, Non4estrvctlre Eraelnstlen, Incivdlnt ail Addenda through Vlnter 191) Adden4uu, Paragraph T 41$
and Artlcl~ Ea as applicable,
!)) AS'Vg Seller Sn4 yr ~ Sture Vestal Cadre It'l4 !dltlen. SFCtlen V, NOF¹destruttle ~
1 ~ ¹ ~ inetlen, ParagrePh To415 end ArtICI~ et SS aPPIIC .
(C) ASTN g 145 10, Paragraph 7 ~ I.
rd) NAC51A 150 '500 ' (Ree. 10 dune 10)p snd ger. 11 Nay 'Igt)) paragraphs 11,5.1.1 snd I goSel e I elo (e) VIL $ 20 )rtyrSN) ~ 17 J>>M 1914 ~ Psrttrsybt 5 ~ 1 and Sel I ~
!t) ulL~ STO ~ 115)A(SN) ~ 15 arch 10C5 ~ ptrtgrae+ha 7 I I ~ 'I I ~ 1 ~ and 7 I 5 Sn4 ~
II ~ rh ¹ C ~ yer ~ lraph 10 ~
(g) aur Stas¹dard f) ~ 47, Vay lgri and Ottab<<r ltri Intludlw,'.F¹nendaent ~ I (t.g .4) an4
) I) P,t), acclaim 4, Paragraph 1 )0.
(h) general glectrlc 7.5. 5000, Rare 1 ( ")I 10) psragraphr )o) and ).t,
. sll'>>Iag test r 'svlCs ¹>ere obtslne4C Su!Curt cs no nercvry I sse 0.0561 s. s.s r sle-. e I I I II \ II ~¹
- . ve tvrther tertlty chat this satori' does not csn
- sin nsrcu
')raring equ(pnenc vas used la Ic~nvtaccur
'l o¹lr s/1>lsl '
7 ss s.
~
s ol r.sss.
basic l/lll l.~
~ lesenc, sn4
~ .
,n~,~
KAONASLof conpnaatlnN
~ ~ ~ ¹c¹sn ~ ~. Iter ~ va cy ss>>rance
't. plansectll - Qvs lty Contre) Chenist
)(rtsr 1. our )etch nvnber appears on the bocten oC sll spray "tnt ~ inert tn4 on che label ot ail ether Nest specifications require case results stated In percenc buc soee trav!re containers'.
parte per ~ Illlen (ppN). TO Cenrert "perCent>> tigurto CO "parte per all!lens¹ I. NCVIEL 150 ~ 1100 ',
nnee the 4ecloal Coot places to the rlcht.
NIL.CTO.)TI, NIL.ST) :I)), spy y) st an4 Agvg 5ection V a)1
~
reculre chat ostorlsls be svb)ect ce ~ prece4vre co eenperate ott roleclio
~ oleents be!ore analysis Cor svltvr sad haleten. Accoidtnt to thHo
~ PeCCCCC ~ Clene, Only these realdVee hither Clean ~ enOS CIIOO thol! be tnaiyted for sulfur an4 halogen. Lever residues shall ) ~ rtystce4. g
- t. The t)are tercltlcstlen tires the rei>>Irs abtslhed st che tine et ssnvfsccvro
'lde and vto oay ~ Icet cbe properties st shy osterlal ~
y¹rn NO, 1144 gelglgp
~I l f ' WV~' Yg lan h '4 ' ft 6 11 'f ~ <<'7/( N H)P1 pI W 'W 1 ~ 8 '4 PZNAL REPORT OP ZNSERVZCB INSPECTION NONDESTRUCTIVE BXAMZNATZONS e OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS BPFBCTS REFERENCE NRC BULLETIN NO. 88 08 APPENDIX H EXAMINATION PROCBDURES PROCEDURE NUMBER REVISION FIELD TITLE NUMBER CHANGE NDE 3.3 2 N/A LIQUID PENETRANT EXAMINATION SOLVENT REMOVABLE VISIBLE DYE TECHNIQUE NDE 5.4 N/A ULTRASONIC EXAMINATION OF AUSTENITIC PIPING WELDS NDE 5 ~ 19 0 FCA N/A ULTRASONIC EXAMINATION OF SOCKET WELDS IN PRESSURIZER AUXILIARY SPRAY LINE (PTN3&4) 24
)
I l
1
- me ~ 1 1
FINAL REPORT OP INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX I CALIBRATION BLOCK CALIBRATION BLOCK DESCRIPTION DRAWING NO.
NUMBER UT-53 ~ 438 INCH THICK, 4.0 INCH DIA D-ISI-024 UT-54 .343 INCH X .893 INCH SOCKET FSK-M-3077 WELDED FITTING TO PIPE MOCK UP 25
77 I'I 0
29 nial f~ 44. Il t. 5 Mi N t Gt P (4 t~ s) 9o
(~ans oneewise ~rett) a~s tctlhc~l '/55.
>.ctstS Wttcat.~bthS 5 /6 I IWttf$ S I cI I
7 FwAStt ~ttR otc ttoakS g ~g 4$ tlt%$ t SABER 5ltRAIc5$ 5$ 0 RH$
bthtntii eeova %~I'liWS DfKftltIJICR5 Q~ bhfhR rlNII RCLOw%D w ~zecrbas f+ reel. ttbtwr~ 5ttttcP ttshr tt . atttbR catt ULrtth5otttC. C'ALtbRhrxvV bLOC K DEbuRA g brttAK'ttttlltCHES leak, FLORIDA POWER 8 LIGHT C~AHY ALI. bitt tlat Cct CtttttbS~ UT-5) - +-.'f38- Tl(Y j
sl 2
1- Fhb IIIC OctS tn ST~ICILE$ 5 bhR crttcIL 5h-tbt, TPbt6 ttW gbybg5
- 40TC S ~N t otq.-
I
~ e4SC CC CICCCCC 01 ~ CCC:
&Crt:at C~ll crt veslll bceuf V ~> 5 C CC < SSS t>O'S ~ . ~,z., O ESI
~~ RMSiBBl
.tA
.pi
~ .1 g
I I g
)l hllf, I ' ~
l I
~ ~
I g
i ~ ~ ~ ~
0 S 0
l t
I 4
i 0
~ ~ i ~ ~ ~. z.yg p ~
y ~ ~ ~ ~ >> "w *.y. ~ c*.~q>> q...v ~" i>> ~ ~~rv g op,, w iirr .
~ q w .a - ~ i v. e
PZNAL REPORT OP ZNSERVZCE INSPECTION NONDESTRUCT1VE EXAMXNATXONS OF PIPING SYSTEM AND
'NISOLABLE COMPONENTS FOR POTENTIAL THERMAL STRESS EFPECTS REFERENCE NRC BULLETIN NOe '88 08 APPENDIX Z LIQUID PENETRANT DOCUMENTATION LOG DATA SHEET IDENTIFICATION DESCRIPTION NUMBER NUMBER
- 3. 3-201 2"-CH-1310-1 REDUCING TEE PIPE
- 3. 3-202 2"-CH-1310-2 PIPE - VALVE 3-313 3.3-230 3"-CH-1301-42. PIPE - ELBOW 3~3 233 3"-CH-1301-43 ELBOW - PIPE 26
LIQUID PENETFNNT EXAMINATIONDATA SHEET N .2-Ro I of~
Procedure No. Data Sheet No.
Revision z Page i Plant Name/Unit: Date:
Il Identification of Item Examined: Z- RC- I o l iso. 00 Examiner's Name: ~~ SNT Level CLEANER PENETRANT REMOVER DEVELOPER Brand: X Brand: Brand: Brand:
C- - Q Type: L- - P-'f g Type: Type: Type:
BatchNo. p&&ZS BatchNo.QJ(~Q BatchNo. ~7AAO 5 Batch No.+~~0 Time Applied~>~
Cleaning Removal Completed ~l+ Cr Dwell TimetPf g Completed ~Dq 5 Time Read 0'i '5 Z-AdcMonai Information
. SketchAttached~< Temperaturehl+I~TThermometer S/N
+0 N
..... Camera Photo Attached Other Ind. L W Up or Round or Dia. or Accept/
No. Location Location Downstream Linear Lenght Reject BATE.
Sketch:
NOTE.: TP TH E CLOSE PROMImfvf C F T H >
POLLoW lM Q K QLQp i ALL Q X&I+'INANEl0$ 5 0E,R.F PER.FOKV E.D S innUL>'W ~ muS L~:
Z,",- Rc- la<o- 4"- t3oz- 4.
Z.', Pt, ta I O- Z 'i- <30'- t A z- $?c.- l.5t o- "- l3cg'-
Z."- RC.- ll(O- '7 Reviewed by lo
LlQUID PENETRANT CIS-5 EXAMINATIONDATA SHEET Procedure No.
Revision Plant Name/Unit:
E, 3. Data Sheet No Page Date:
I,f 3,3- Zo Z.
QZ;I( -Rc l
tdentification of Item Examined: Iso: OQ -A i Examiner's Name: ~ SNT Level CLEANER Type:.
lA~ Brand:
ype:
- F>>
REMOVER Brand:
ype: - -
'EVELOPER Type:-
- ~X - -58 Batch No. '22bhQZ9 BatchNo. 9MM9 BatchNo. 3~~5 Batch No. 99> @<iR Title Time Applied~C Cleaning Removal Completed ~COO DwellTime >7 C 7 Completed O'AD%5 Time Read A al Information Sketch Attached NO Temoeratortarthtttrr!SLIT Thermometer S/M N CameraPhotoAttached~+ Other Ind. L W Up or Round or Dia. or Accept/
No. PATE Location Location Downstream Linear Lenght Reject Sketch:
H()~E. '. QU< TO 7 HE- C LWE. PR.OX)M ll //'l= T'E FOLLOWINth W EL+5 ALL EXAM NATION J I R. i=O RME O 6 IVt u L rorNEOIAS LY I
Z-,", Rl" {3iO- - (BC'- 4 Z"- Rc.-
z,", l5lo- Z.
t 4-,",- l~-
4-,",- RC
~'r- gG- tSOC BOb- lA Z."- RC= L'5JD-Rt=- (blO-W
+ ~<<- <cc- 3- gv n oZ C-Ir:WO
'70 ~
Reviewed by ck I Form 3325 (Hon45ocked) Rev. 10l88
UQUID PENETRANT Procedure No.
Revision Plant Name/Unit:
Identification of Item Examined:
EXAMINATIONDATA SHEET Wl Data Sheet No.
Page Date:
Iso;
~ oi~
6 0
~
8 23o Examiner's Name: SNT Level REMOVER DEVELOPER Brand:
Type:
Batch No. ~ "
Brand:
- 8Type:
Batch No. ~222 Brand:
Type: >C -
Batch No. ~4~
Brand:
Type:
Batch No.
Time
~~~9 Campleted J~S~~ DwettTime >VO t Removal Campteted ~t "I ~ Time Applied~i'leaning Read~hg SketchAttached~> Temperatvre~ Thermometer S/N Camera Photo Attached No Other Ind. L W Up or Round or Diaor Accept/
No. Location Location Downstream LInear Lenght Reject Sketch:
PD jG.'~t~1 dC~fiu ~7 TO<. Of- Veld, ~64'<t~~~'~" 9'~"
rclcvcn P~C. T~ ~C C.(AS,C OCa X<m,+y Or 'the r -~~cd 5'a w>Tao co/ ~ l y."
POOavl e~g &CQ55 >All GW~inc ft
<c.rc, t/d C 1)+ 0"- C H 'l'3O< - lA w~ld4a 3'Ck -L3ob-"LS Reviewed by Vo a>>
LIQUID PENETRANT CIS-5 Revision d d.~ EIOLMINATIONDATA SHEET Data Sheet No.
Page
~ 3 23 3
( of Plant Name/Unit: Date: > -> 3-ll Identification of Item Examined: Iso: oc Examiner's Name:
n SNT Level CLEANER REMOVER DEVELOPER Brand: Brand: Brand: Brand:
Type: - c.- Type: Type: c-7 Type: - z i/f Batch No. +~~ Batch No. ~~~ Batch No. ~17@~07~ Batch No. ~~~
Time Applied t rrO Cleaning Completed ~<~ DwellTime I~'f<<~~
Removal Completed I'r~ Time Read~<> 0 Additional Information Sketch Attached ~O Temperature ~~ Thermometer S/N Camera Photo Attached ~0 Other Ind. L W Up or Round or Dia. or Accept/
No. Location Location Downstream Un ear Lenght Reject Sketch:
goTg .'ae,7 z~ Ji~geo ~ +7 Toe. oF~QQ ) 3CO swee pse77~f ggomcgrru'~ rk rehcua W
)qogtekrk Hg 0F ~C OIelotA a~) VJ4 )L5 k]L
~pre. pmpp( w ~d ~'~ t>~t tco~sly.
~
Ega> no9eo'~y
~ g$ ~ Z'<g - C'3O t -- HO t
w uk'3 -<H -L 5<'l < ~
Reviewed by Fam 3326 (Non4tocked) Rev. 10/88 d ' ~
- ' 1'
4 1 P ~ ~jp I'g "fp','p)h
" 5 / lP Q. 1,<, Itj '"O'I 'p'4ifgp Pgl @ZAN,
RZNAL RBPORT OP ZNSERVZCB INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLB PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX K ULTRASONIC BXAMZNATZON DOCUMENTATION LOG DATA SHEET IDENTIFICATION DESCRIPTION NUMBER NUMBER 5 '-43 3 n -CH-1 3 0 1-4 3 ELBOW PIPE 5 '-44 3 n -CH-13 0 1-4 2 PIPE - ELBOW 27
PINAL REPORT OP INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SXSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX K ULTRASONIC EXAMINATION DOCUMENTATION LOG DATA SHEET IDENTIFICATION DESCRIPTION NUMBER NUMBER 5 '9-1 2"-RC-1310-1 REDUCING TEE PIPE 5.19-2 2"-RC-1310-2 PIPE VALVE 3-313 5.19-3 2n RC 1310 2 PIPE - VALVE 3-313 28
- I Zone/iso 0 E/& Odg CALIBRATIONDATASHEET CIS-1 e{ Plant/Unit Oats Sheet ml Comp/System P sge / of d
1 INSTRUMENT SETTINGS SEARCH UNIT Procedure No. h/bC ~0 0
Mfg./Model: IL E omorqre:~~ M odmg~{1 gp Rev/Chng. No.
Serial No: <1/3Z ZZ Fixturing lifany): cA Delay: ~ /i Range: ' Brand & S/N: 70 or
~d{/
M'tl Csl: Size & Shape: '~+ ~i~ 60
{F Ere o rl 50 Each Major CRT Oiv. en ~ 3 F eq.: ~>+ Mode: SE REE ~ Freq ence:
40 CRT Calibrated in: ~ound~Pst Depth A/~ F rz'o Filter: Rep. Rate:~+t~E Mearured angle: 30 Csl. Direction: Axial, Circ40ih) e OEC/Gate: A {farl Cabie BhC -%7 D Scan Area: 0 WRV, 0 Mt'I e Weld, ~II \o W ld Art Gain: C P Zrg
..,-~50 0 INST. VERT. LINEARITY I8 CX 1 2 4 5 6 7 8 9 10 Scan Sent: AK AMPLITUDE AMPLITUDE Edq r lr h: R{A 1{oh md{eh RECOROAELE High Low High Low INDICATIONS COMMENTS/REASON FOR ITEM EXAMINATIONAREA/WELD YES NO GEOM. INCOMPLETED SCANIS) TEMP.
3 -ch'-Zyo/- 'fS 5 SETN/zEN Cz5 ~o 7.so" zo
/FW V PAv'4 5M/F'xTEb v8 bus <o 3 ~D ~DB ~D rnrivaE vo 4V Aoiu.
v oF rr/E Ec.Bowl x,v/I ~HE Q.
ALSO 4~~B~Z o u7-r/rI o c AMPL CONTROL LINEARITY
/I/O c . u. -5 tt) E'D zu lxcu. Initial 5ds Result oF a.v-V . uv-53 ~s re sAf Hoes L 80 A'E 43 0 V E EA'S1ir dr 80 -12 po 40 g8 20 +12 EXAMINERS ~ LEVEL ~ DATE CAL. CHECKS TIME Initial Cal.
Intermed.
I z-i9'-O'Q Intermed.
Intermed.
REVIEWERS zP~IFQ F{n.l C.li /'4'D
Zone/Iso 0 5 OO CALIBRATIONDATASHEET CIS-1 5 I Plant/Unit / h/- Data Sheet 4 ol rr Comp/System LXNE Page INSTRUMENT SETTINGS SEARCH UNIT Procedure No. 5
<< O /. lib Rev/Chng. No.
2./3 ZZZ Serial No:
M tlCal: /~.4 lo Site & Shape.
~za
'5'/A Il 70 Cal. Block Temp.
Thermometer S/N
..::E I 9 Each Major CRT Oiv. ~
r/
50 Frequency: CRT Calibrated in: Sound Path Depth
~<<<<<<<<~~+ Ma<<<<ed Ingle. Cal. Direction~Axia Circ., Both Cable:
I N'C- Scan Area: 0 WRV, 0 Mt'I 20 MOVS 't h'ra Cpg<<I<<<<<<1 QLr 10 to Weld II .to Weld B INST. VERT. LINEARITY ScanS ns: A<<0 0 1 2 3 4 5 6 7 8 9 10 AMPLITUDE AMPLITUDE 6dB switch: +~ 14dB switch: /t ~ RECORDABLE High Low High Low INDICATIONS COMMENTS/REASON FOR ITEM EXAMINATIONAREA/WELD YES NO GEOM. INCOMPLETED SCANISl TEMP.
1 ]00 <0 6 SD 25 3 -C//- /30/- 03 (I/l KrwE& 4/IZ5 <n HO S'8 F Ark'<8
-rn /'z, Y vo SCA/y',xwzrs XiV/I/E'd RAdW.5 OF y//E EC8OW'LSO a.LL s Wxrrt/ rtfE l5 4 7D
~0 ~2, 35 9 zD
/D
/D HO1 E': Q.T / I doE' AV Zhl SD AMPL. CONTROL LINEARITY OvC E5 T- odAS 5 Xnl EQ Initial 6dB Result u.T-u v-5 Z vs sdeE 60 C y//XCA'Aie55 A/ rE nrE 60 -12 ACotLS C P~PEQ 40 +6 20 >>2 EXAMINERS LEVEL ~ DATE CAL. CHECKS TIME Initial Cal.
I ntermed.
I<<
LEVEL DATE Intermed.
lntermed.
REVIEWERS ~~~y ~z&JZg Final Cal /OS'F
INDICATION REPORT SHEET C IS-2 Ou=f 5X E.
Calibraticn Data Sheet Number: In Zocaticm: Examiner TC-1A- e RA br.u5 CKNTEA?L1hrE Item Identificaticn: ii 3-c -/ ol- 3 Wo Incatim: Ol E mi r: C-1A-Level WKL N7 Ocapmnt %idmess: .5 D Dimeter Scan Area: wel I to weld -~~-wo S.U.
Angle IOC. RXABKS 20 20 z5 51
/.7'f /.3 / 8'7" 0 708 u.p 8 5 .9(o Additiceal Remade REVI1MR(s) Rtther Evaluaticn Requ~ y~
s'e H3 BY CHKD. BY SHEETiXO PROJECT NO ~A g! ~
zJ I I I I I
I I I I
r c I ~
I s
$ ! I ' I I
I
\ ~ ~ I s ~ I I IP+
g ) I I I
I I
I I I I
~
I I I I I I I !
I j
I
~riV s,p '>rig(V p vvr ~, vier y, .vr,, i ;r. r.r " v v;: V i y .r r ~ r"~e- . v .e ~; *,-;.w~. - -, ~; q";, ~, i~., s i ~ -. ~ ~ -
g',w } i@~~ ~,yc >.
Zone/lso CALIBRATIONDATASHEET CIS-1 Plant/Unit Oats Sheet Comp/System Page of INSTRUMENT SETTINGS SEARCH UNIT Procedure No.
Mfg./Model: -98 Exam angle: ~~ Mode:39g0 Serial No: l, 2- 2 Rxx Exx (N(): I- C. ITE ap Cal. Block No. T Delay: ~~ Range: Brand SE S/N: 70 Cal. Block Temp.
M'tl Csl: Size 66 Shape: 60 Thermometer S/N o
Damping: Q}~Reject: Style/Type: Each Major CRT Div. AE Freq.: ~+ Mod>> QHGill Frequency:
40 CRT Calibrated in: Sound P /Depth Filter:~~ Rep. Rate J~cQ Measured angl ~: Cal. Direction: Axial, Circ.~ot
/
OEC/Gate: Cable: Scan Ares: 0 WRV, 0 Mt'I 20 Video:~E'~ 600V Switch:Lhl~ C pl tbrand: 0 ~s4 10 to Weld, to Wel RX 2D/
Gain: Couplsnt batch: INST. VERT. LINEARITY 0 1 2 3 4 6 6 7 8 9 10 Scan Sens: CI 2- AMPLITUDE AMPLITUDE 6dB switch:HZ'4dB switch:8~ RECORDABLE INDICATIONS COMMENTS/REASON FOR ITEM High Low High Low EXAMINATIONAREA/WELD YES NO GEOlL INCOMPLETED SCANlS) TEMP.
)'-cH-t 01- 2.
66 P '/0 PAT uE To
,~d~d, 3Q u5 CF = .
M L P T AMPL. CONTROL LINEARITY NoT Initial 5 dB Result 80 ~3 5 E /VOm 80 ~ 12 40 x6
~7 5 ~cAL gd E x 5 CAL. CHECKS TIME 20 +12
~)
EXAMINERS D. LEVEL~i DATE z-zg- 70 Initial Cal.
LEVEL zv DATE z-zV-gg Intermed.
Intermed.
Intermed.
REVIEWERS Final Cal, J~ Q
vA: - av ava v ~ ( a '0 a wa 8 A E ~ -= AA 'as ~ aa,wnia VA">>~ A,akw ~ av',aA v ', a a. a " g, T A A aL4 a 4a A A a'aaara ..* w aa ~ ~. 4" '*.-q .' ~
Zone/Iso 4 4 O~ CALIBRATIONDATASHEET CIS-1 Data Sheet Plant/Unit Comp/System ~<44~
Mlg./Model:
Serial No:
INSTRUMENT SETTINGS AILTKRIht/%
2J 2 SL- zia Exam angle: ~SEARCH UNIT Mode: :5@A gp Procedure No.
Rev/Chng. No.
LLT 5 3
~*
Csl. Block No.
80 Dajag:~ZRange:~ Csl Block Temp 'air 5 M'tlCsl: Z SL Size 6L Shape 60 hl Daanjgnjj:~+rjj+tj ajanra: aDFa 50 Each Major CRT Oiv. ~ 3 2 Z5 ~gOg L6 ~
~f Freq.: Mode FrtKIUencpt a CRT Cahbrsted m. ound Path DePth 4p Filter t ~+ Rep. Rate: ~//H0 30 Csl. Direction: ~xi Circ., Both OEC/Gate: A Cable. AC /178 Scan Area: 0 WRV,~ 0 Mt'I
~
Enn:~N J
.-<<j~a REEVE :
to Weld II to Weld Gain: Z.O 18 INST. VERT. LINEARITY 0 2 3 4 X A 1 5 6 7 8 9 10 Scan Sans:
6dB switch: /I 14dB switch:.. he RECORDABLE INDICATIONS COMMENTS/REASON FOR ITEM AMPLITUDE High Low AMPLITUDE High Low EXAMINATIONAREA/WELD YES NO GEOSjL INCOMPLETED SCANlSl TEMP. lOO So 6 5o 25 3 -I" -/30/-'I/2 BA IIhzaijh'I 15 vo /. z5 s<AhI S'g r , ~o 2 ~D 20 z,xhtsx.veD vo hh'a. v Pew btLe 7o , ~o Xhthhth WCh OI= <h/E KC8OHh AL50 4 7D BALLL ex SA'/5 .
, ~o ~z~j 5 NCn E': Llv-sl4 oES NO1 CO 'X AMPL. CONTROL LINEARITY c E'LT-53 2A/ Lf'ECL Initial h,dB Result Or 7-4/4 kT-53 S fN SAAE 60 .E 3F PhH Xmas'wcAhth~j hshh 8S %PE'C 60 -12 ZO 2'E5. 40 t6 20 +12 EXAMINERS ~ 'EVEL ~ DATE CAL. CHECKS TIME Initial Cal. O Intermed.
8+
LEVEL DATE Intermed.
REVIEWERS F..
Intermed.
in>>l Csl, /D5g
INDICATION REPORT SHEET C IS-2 Calibration Data Sheet Raher++~~ Zo Zocaticm: Examj.ner.TC-1 ve Iten Identificaticn: ig ce~awcxma 3 -cu-/ o/-VZ Wo Iocatica OF W L Ex min r: -1A- el X7 one t Dianeter at 'Ihidcness. - 50 Scan Area: to I to weld z.-zoo INDICLTXCN IZtKKH S.U.
of IDC.
z.
5'5 VS IRC 20 20 5/ .(pd ./.o",bd Ii 5 0
~P.
o ] A<8 ~6 AW .
3 (o o ~ 8'/ 75 fl 80 /.& Q.5.
Additianal RaaMcs:
REVII5KR(a) Further Evaluatica Required Yes
sv CHKD. BY DATE QFPL I'!;
Bi. ', oi.
I 3 .c.if!-I 0 I
I (
I UZI I
I I !
I
~
I!
I I
I
~
I I
~
)
~
i in@'
I I
I I I ~ I ~
~
I I
! I i '
I I I .
I ~ I I I ~
I I I
I I I I I l I ~ I . ! I j
~
I
o -A CALIBRATIONDATA SHEET Zone/iso Plant/Unit N- CIS-1 DaisSheet . t /" I rl Comp/System csSuii z cw Page of Serial No INSTRUMENT SETTIN Mfg./Model: I' Exam angle: ~SEARCH UNIT Fixturing lifsny):
Mode: ~~<El I0 Procedure No.
~
Rev/Chng. No.
>> .. ul-pp 80 .
D...:~>5
~
R SI S/N: 70 n
M'tl Csl: Size SI Shape: 60 Dpllp llÃM+~plpcc~ Rate'rand Style/Type: 50 Each Major CRT Oiv.
Iz F pq.:lkpal8p>>L Mpdp Frequency: CRT Calibrated in: Sound Path Depth Filterl~ Rep. Measured angle:
30 Csl. Direction: ~Axial Circ., Both DEC/Gate: C'bfe: Scan Ares: 0 WRV,~ 0 Mt'I 20 Video:~i BOOV Switch:~iCC Couplant brand: Ya 10 to Weld, II to Weld
~
Gain: Cou plant batch: INST. VERT. LINEARITY 0' 2 3 4 5 6 7 8 9 10=/."
u+2J C AMPLITUDE AMPLITUDE 6dB switch:Cled 14dB switchtCK4~ RECORDABLE High Low High Low INDICATIONS COMMENTS/REASON FOR ITEM EXAMINATIONAREA/WELD YES NO GEOM. INCOMPLETED SCAN(Sl ~-n TEMP.
6 ~C.
/I
-Rc-( +u
, ~o 4
70 33 9 M /0
, ~d 10 AMPL. CONTROL LINEARITY Initial Q dB Result 80 80 -12 40 +6 20 t l2 CAL CHECKS TIME EXAMINERS 'EVEL DATE 2-/8- 4 MRC t. D'7 rp
~/I-i Inter med.
LEVEL W7 DATE REVIEWERS .0 >>>'$P;c'>>
1%.1444 CALIBRATIONDATASHEET
'I Zone/Iso Plant/Unit CIS-1 D.t.Sh 5 I'I- I ti l
Com/S stem > 4 . ~, c Page of INSTRUMENT SETTINGS SEARCH UNIT P.ocedure No.
Hflo el rdrK Eaamaoolm~ 4/
~e"I Mlo/Model: Mode%~1 Rev/Chng. No.
gp
,;...:~7777 77 ;,.;, L.:
a I
E Oelsyt ~e~ r/ Ranger II Brand & S/N
~ rl 70 II d'hermometer Cal. Block Temp. A M'lI Cal: S/N
- t I/
/ 50 Each Msior CRT Div. 44 ~ /~
F eo.:klaMQWl Mode ~df Feoaoeoev 40 CRT Calibrated in: ound Pat Depth Ilc F ilter: ++ Re/>> E.tc. i>> Measured angle:
s 30 Csl. Direction:axis Circ.. Both OEC/Gstet 4 8u/'-wrO Scan Ares: 0 WRV, 0 Mt'I V doe~ EEEV Ew leo: + Co Faoel aemd: tt 10 to Wel II to Weld Gain: ph INST. VERT. LINEARITY tl') 0 1 2 4 5 6 7 8 9 10 =/.~"
2o 2 I-'~ok)>
Scen San,.
.g- J.l'.yd .8'si~ AMPLITUDE AMPLITUDE 44E I IaavM/g aadd oellaa.~ag AECDADAELE High Low High Low INDICATIONS COMMENTS/REASON FOR ITEM EXAMINATIONAREA/WELD YES NO GEOM. INCOMPLETED SCANIS) TEMP.
1 ~u" ~d6 ~d ~2 3'/0- l.e sc; y/Em P V'6 I '/$ 7 ~D ~47 4 27d -
35'o 9
/y AMPL CONTROL LINEARITY Initial b, dB Result 80 80 -12 40 g6 20 t12 CAL. CHECKS TIME EXAMINERS LEVEL DATE l MalCM ~0
/ Intermed.
LEVEL~ DATE Intermed.
REVIEWERS ~ /7 Jcr < ///'/ /Q// Fl IC I
/ w//
INDICATION REPORT SHEET 3 of 3 Calibration Data Sheet Number: Zo Zacatian:
TQ g Ex i :TC- A- vel Item Identificaticm: 2" Q Q I31g ( Wo Zacatice: Q5 T p )J E i : C-1A-Level n-Ocaponent 'Ihickness: t~i =, ec Dian ater . ~
Scan Area: to weld I~ 90 S.U.
Angle of IDC.
DAC 20 50 20 goal OI/ os ( co Ir o ekr au 3</ zg gy~gP'/ ge/ass/ I / /(/cAh i f4e ce~ ~( /n/sl / sP o// f~ ~~ (~+ /'ger,~
REVIEWER(s) Bxrther Evaluation Bapured Yes
Zone/iso CALIBRATIONDATASHEET CIS-1
~ ~CI~ l t 2.
~
Plant/Unit c//unrig Oats Sheet SE Comp/System F 8r Pape INSTRUMENTSETTINGS SEARCH UNIT . ~ ..
MfgJModel: E arrl mal:
0 Mode:~P gp Rev/Chng. No ~A Serial No: 1 Fixturing lifsny): Cal. Block No. //l Rerav:~'amp:~ tr Brand & S/N 70 M'tl Csl: Size & Shape: 60 Thermometer S/N 0 ll Damping:~LE Reject:~'r~.t Style/Type: 50 EaeaM IorCRTOiv.
~8Mw/LM~: Q~/. Frequency:
40 CRT Cshbrated m Sound Pat Depth O
Firmrr~Trt'ep. Rare~REM Measured angler 30 Cal. Direction: xia Circ., Both OEC/Gatet
~,
Video:
Gsint A/ 600V Switch:UgC{
AfC -NTQ Coup!ant brand: '0 20 10 Scan Area:
J 0 WRV, 0 to Weld Mt'I II to Weld INST. VERT. LINEARITY 0 1 2 4 5 6 7 8 9 10= i.2 Scan Sent: AMPLITUDE AMPLITUDE VFA
~ $ L der/Etym Og 5$ tgfprR~
6dB twitch: 14dB t itch:@LE~~ RECORDABLE High Low High Low INDICATIONS EXAMINATIONAREA/WELD
"-8.c-]
YES NO GEOM.
COMMENTS/REASON FOR INCOMPLETED SCANISl Fr ITEM TEMP 6'r-le ~<6 M>
g ap f~& $ 4/ 0EE S ~~ 8 TI$
o"-
8~
~t I AMPL. CONTROL LINEARITY T
Initial !5 d8 Result
) 80 ~r 80 -12 40 tE
~ET
~
=L e
20 t12 t
CAL. CHECKS TIME EXAMINERS LEVEL RATE Itr IC I. ~R x1 aT e
te LEVEL DATE Intermed.
I at ~
~~~
mee. ~P>
'r eS REVIEWERS <
F .I C I. ~l< V INDICATION REPORT SHEET >.l9-2. CIS-2 of Calibration Data Sheet Number: Io tucatice: Dg Ex i TC- A- velI Item Idectificatice: 2"-g (3)II-Q 'N Iocaticm: )( p g () Exam'0 r: C- -Level (valent Thic)mess: Diameter = . J e 2" Scan Area: I to weld C-Angle 20 /0 CU 50 20 .4o'.U. IOC. /E 4> @au Wb~ t adciticoaI Hem~a;, +5<<pz/~ul <<[/z fy $ e p I~@ <<~ frs~ o" f'ca'~ J C-c >) gee /u Afvr copgirc rwhip, REUHMER(s) Further Evaluation Required Yes >, I 5'- Z BY o*rg ~ SRE- 43 Ot CHKD. BY DATE ~ ~O PROJ ot3 I I I I I: I I I I ( Ig I ~ i I I I I I ) 4 ) I ~ i I I 4, I ~ I I ~ ~ I ~ I I 4 I I I I a I I I I I I I I ) I I ~ g I I i I I I I ~ 4 I I ~ - I~ w . ~, q at I I g,at F I a(,I IF', t,g ~ar FF< I)h AFI44 Pal .Fg I I I <<I I* 5 gars I, I h.' v~ ~ I r ed Zone/iso Plant/Unit Comp/System 1 v INSTRUMENT SETTINGS 'a -A -P eSurrs er SEARCH UNIT CALIBRATIONOATA SHEET CIS-1 Eme ~or~ Data Sheet Procedure No. ~ / Mfg./Model: r uf drh Exam angle: ?'I-) CB Mode:~ g0 Rev/Chng. No. h Serial No: Fixturing lifsny) t vcr.vv ~* 80 . O~ 1 Delay: ~'ange: Brand Si S/N: 70 Cal. Block Temp. / ~ ? M'tl Cal: Damping: MMR act: Freq.:QSsQtRa J el Modrx ~~d< ~i~ Size SE Shape: Style/Type: Frequency: 5 60 50 40 Each Maior CRT Die. CRT Calibrated in: II Sound Path/Depth ,1 0 Filters~'ep. Rste~d>el Measured sng4t I EE) 30 Cal. Direction:(A~xial irc., Both DEC/Gate: Cable: -Ahr 20 Scan Ares: 0 WRV,~ 0 Mt'I ~ Video:3W 600V Switch:MW Couplsnt brand: 10 to Weld ll to Weld Gain: dj Couplant batch: INST. VERT. LINEARITY 0 1 2 3 4 5 6 7 8 9 10 Scan Sans: 3 AMPLITUDE AMPLITUDE Edh irch:~lech awircmMi EXAMINATIONAREA/WELD YES RECORDABLE INDICATIONS NO GEOMe ~~Et I COMMENTS/REASON FOR INCOMPLETED SCAN(S) ff fO 3 rpm 055rJ~ ITEM TEMP. High ldO Low '~5 6 1 ~High /I'o Low V e 7 Cc. a 3 4 5 ~~ 7() 40 9 3X 8 ~~ N /d AMPL. CONTROL LINEARITY Initial Result 80 4'o 80 ~ 12 dto e6 20 +12 AE je <as e ',< r, <,y q-ega. ~, vp.-,y* qvw~w > v i e y v w ~ ~n re r...,,, qadi p orrery'pqr ~ pygmy" PZNAL REPORT OR INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS ERPECTS REFERENCE NRC BULLETIN NO ~ 88 08 APPENDIX L ENGZNEERZNG RECOMMENDATIONS DOCUMENT NO. SE&PT-SSAD-7814 29 SBPT CSAO 701'ev. D TURKEY POINT UNITS 3 AND 4 (NRC BULLETIN 88-08 THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEM) IDENTIFICATION OF UNISOLABLE PIPING AND DETERMINATION OF INSPECTION LOCATIONS August 1988 P. L. Strauch N. Ucak Verified by: am or Approved by: n a ~ <<' =h% lj t 'I f ~tel, f, " 'g ~ )f ',, ~, 8 V 'F 0 pQ'l~gg SRfT ssAD-7s14 Ital. 0 NRC BULLETIN 88-08
- 1. PURPOSE This report provides the basis and conclusions of the evaluation of Turkey Point Units 3 and 4 unisolable piping systems and components for potential thermal stress effects as described in NRC Bulletin 88-08 (June 22, 1988),
Supplement 1 (June 24, '388) and Supplement 2 (August 4, 1988).
- 2. SCOPE This report addresses items 1 and 2 of Bulletin 88-08, "Actions Requested" for Turkey Point Units 3 anc 4.
(a) Determination cf 'unisolable sections of piping connected to the RCS which can be subjected to stresses from temperature stratification or temperature oscillations that could be induced by leaking valves and that were not eia'.uated in the design analysis of the p'.ping". (b) Oetermination cf locations for nondestructive examination to "provide assurance that :here are no existing flaws". in addition, inspection guidelines are vrovided to enhance the likelihood of detection of indications.
- 3. PROCEOURE o A plant specif'= systems review of piping attached to the reactor coolant system is performed to identify any unisolable piping which may be susceptible to the thermal phenomenon outlined in NRC Bulletin 88-08.
o For any unisolmle piping identified, piping isometric drawings are reviewed to detarrine critical locations where in-service inspection should be perfc~. 31li s/Ol!54L10 SENT-SSAO-71'll Itev. 0
- 4. CONCLUSIONS The systems review to determine unisolable sections of piping (item (a) of e
Scope) is documented in Attachment l. In this evaluation the unisolable pipi~g has been defined as the piping fran the reactor coolant system to the firs: check valve in the auxiliary piping under consideration. It is concluded that portions of the following auxiliary lines in the Turkey Poin: Units 3 and 4 plants must be consHered under Bulletin 88-08: Charging pump to pressurizer auxiliary spray line c Charging pump to C hot leg The =etermination of locations for nondestructive examination (item (b) of Scope) is documented in Attachment 2. It is concluded that the locations iden=ified in figures A to 0 need to be nondestructively examined under Bulletin 88-08. If any pipo welds exist between the welds identified, they . shou d also be included in the inspection. Guidelines to enhance detection of poss-hie indications are provided in attachment 3.
- 5. ..=FERENCES
) United States Nuclear Regulatory Commission Bulletin No. 88-08, June 22, 1988, "Thermal Stresses in Piping Connected to Reactor Coolant Systems."
- 0) Isometric Orawing 5613-P-661-S, Sheets 1 and 2, Rev. 0.
=) Isometric Drawing 5614-P-782-S, Sheets 1 and 2, Rey. 0. =) P 5 ID Drawing 5610"M-410-91, S.;eet 2. e) P 5 ID Drawing 5610-M-420-3, Sheet 3.
- ) 'eat and Mass Transfer, Eckert, McGraw-Hill, 1959.
TURKEY POINT UNIT 3 AVXILIARYSPRAY LINE SE&PT-SSAD-7814 Rev. 0 Bast Nttal TOP Inspect only shaded portion of line. I FZOhl T I ~ SECTION BM w 1d SECTION A ~~g F PESSURIZER A 0', b<g~~ ~4'o qA gl 0 '. ~]W 10 181 I 1 J' )g. %g 9e >o >o 9 99' ~ p 9 r+ 9p 99 99( FIGURE A +rp 99~ lr~ TEMPERATURE ONITORING LOCATION (As close as pcssible to valve outlet) Ref: Isometric Drawing 5613-P-661-S Sheet 2 of 4 SE&PT-SSAD-7814 TURKEY POLIT UNIT 4 AUXILIARY SPRAY LINE Rev. 0 Base 8 tal Inspect on]y shaded portion of tee. sccrioH 8-S sEcTiON A-A gQ h h + yl ~OO J1 gab ~OO gr ,r4 +qO I1 aO~ gC 1~1 I ~gO Pl~i B Temperature Monitoring Locati"n (As close as possible to va-'v<<utlet) Ref: Rev. 0, Sheet 'f Isometric Drav ns 5614-P-782-S 3 TURKEY POINT UNIT 3 SE&PT-SSAD-7814 Rev. 0 CHARGING PUMP TO C HOT LEG Temperature Monitoring Location (As close as possible to elbow weld) 20 pV g+ bb eyb %0 0~ 00 ~pl +0g 0~~ gO >o~ l~ yO J 8 0 y 80~ +S CU AJ o J~~ if@ 8g FIGURE C ~ J Ref: Isometric Drawing 5613-P-66l- S 'Rev. 0, Sheet 2 of 4 TURKEY POINT UNIT 4 SEkPT-SSAD-7814 Rev. 0 CHARGING PUMP TO C HOT LEG SHORT RADIUS ELBQV HQT LEG LOOP C 34'.D. Iran 20'H g+~ ~w ) ~n 2S'H ~g N uI ~l h l;g Ceepq 20'H e lr~ FIGURE D Temperature Monitoring Location (As close as p=ssible to elbow wel< Ref: Isometric Drawing 5614-P-782-S Rev. 0, Sheet 2 of 3 SE&PT-SSAD-7& 14 Rev. 0 ATTACHMENT NRC BULLETIN 88-08 EVALUATION FOR TURKEY POINT PLANT UNITS 3 4 4 SYSTEHS REVIDt In general, this phenomenon of thermal fatigue of unisolable piping connected to the RCS, as described fn the NRC Bulletin 88-08, can occur whenever the connected piping is isolated by a leaking isolation valve and the pressure upstream of the leaking valve is greater than the RCS pressure (2250 psfg nominal), and the temperature of the. fluid is significantly cooler than the RCS temperatures. The only pressure source available fn the Turkey Point plant which fits this criteria is the normal charging system. During normal conditions, the pressure at the discharge of the charging pumps is approximately 2350 psig. Our review identified all flow paths between the discharge of the charging pumps to the RCS. Lines identified included the auxiliary spray line and the charging line to C loop hot leg. The following fs a review of each line. Figures 1 and 2 depfct the CVCS auxiliary spray line connection to the main spr ay lines, for Turkey Point Plant Units 3 and 4, respectively. During normal operations, the auxiliary spray line fs isolated by closure of valve 311. Valve 311 fs a three inch operated globe isolation valve (3-IA58RGP). The differential 'fr pressure across the valve fs estimated to be approximate1y 50.0 psfd, under normal conditions. The check valve 313 (2-C58) is a two inch lift check valve. In-leakage from the high pressure charging line across valve 311 would result fn eventual leakage of the fluid volume between valves 311 and the check valve 313 into the RCS. The temperature upstream of closed valve 311 fs around 493 F based on the regenerative heat exchanger tube side outlet temperature. Point E on Figures 1 and 2 represents the )unction of the CVCS auxiliary spray line with the main spray lines. The temperature at point E fs mafntafned at approximately cold leg temperature of 546.2 F by the 1 gpm spray flow. Note that some cooldown due to heat loss typically occurs fn the main spray line from the spray scoop to point E. SESPT-SSAD-7814 Rev. 0 From Figures 1 and 2, ft fs seen that there is a long cold trap between points 8 and C downstream of valve 3)1. Although the line is insulated, any leakage through 311 will very likely be cool- before ft climbs uq 50 feet of pipe and reaches point D. Point D is expected to be hot sfnce ft fs located close to the main spray line. Therefore, ff the va1ve 311 leaks, cool leakage entering the warm section from point D to E could present a thermal stratification and cyclic fatigue problem downstream of the check valve 313. Figures 3 and i depict the CVCS charging line to C loop hot leg, for Turkey Point Plant Units 3 and 4, respectfvely. Ourfng normal operations, this line fs isolated by closure of va1ve 3108. Valve 310S fs a three inch afr operated globe isolation valve (3-IA580EP). The differential pressure across the valve is estimated to be approximately 0 psfd, under normal conditions, and the amount of any leakage fs expected to be minute. The check valve 3128 (3-C58) is a three inch swing type check valve. Nth a small amount of fn-leakage from the high pressure charging line through valve 3108 would result fn eventual leakag of the fluid volume between valves 3108 and the check valve 3128 into the RCS, and the crackfng pressure of the check va1ve wou1d create a cyclic phenomena by periodically burping fluid as pressure builds up between the isolation valve and the check valve, due to the leakage. Under the normal charging conditions the temperature of the charging flow around the valve 3108 is expected to be 493oF (point A in Figures 3 and 4), the regenerative heat exchanger tube side outlet temperature. The temperature of the fluid downstream of the check valve 3128 fs expected to be close to 600 F by virtue of its location above the RCS hot leg (pofnt D fn Figures 3 and 4). In Unit 3 layout (Figure 3), there fs a . cold trap between the downstream of valve 3108 - point A, and point 8. Similarly, fn Unit 4 layout (Figure 4), there fs a cold trap between points A and 8 and the check valve 3)28. In either case, any leakage through the valve 3108 will very likely be cool before ft, reaches the check valve 312S although the line fs fnsu1ated. Point C fs expected to be'much hotter since it is located close to the hot leg. Therefore, if the valve 3108 leaks, cool leakage entering the hot section from pofht 8 to C could present a thermal stratification and cyclic fatigue prob1em fn this section of piping downstream of the check valve 3128. "Cold Trap" refers to the cooler water at the bcttom of a vertical pipe section. "Cool" re=ers to a temperature which is approx& -=ely ambient (100'F) ~ lo.l5 Qy Sa'3 (o~n g) ~ $ o}Q ~ ~ S'o.p XSq( o st'0,e 4 C,a'- l$4g X cA 77j W C a O I Vl Vl 00 .A A "4k,. w ~ I Pl@.vs, 2 4 IL AL 'p Li&K (u~n. 4) 7f.o iud e.1 I ~f.: <<<4 ~~a> >-CL Co~ y]'%0 Owe'Q NO . s:'Qa a~ A.51I C.o jv~. Chp. g ~ ]r E'l. I ~ 1c'g 4 4 4Q. ~ Cll 0.%R'4:S A tO t1 lg.yg O I ~l 1 IP V. 3.4 523 I-ov I 7.7b V 4 MCk t A CH~<+C. UgK T~ L~P C HoT Lac. C.as~aw q) Rcg: st.i)-P-aCt-S, fh.2 p ~ 4 's m.st'peO 2'g~ 'LCL 27.1L 5 C ~-%5 s.s I CAp ~ (.ol ~l Q-IN'A I Zt. iS.% is:s' C.wt o.la.'F6e4.~. ate'olg % l0 CA Jot 4 0' <r iy~ I -1 .~ ,pl 'c"., s Elan-CLLO-731i ltev, o ATTACHMENT 2 BULLETIN 88"08 EVALUATION INSPECTION LOCATIONS
- 1. 0 METHOOOLOGY identifies unisolable sections of piping connected to the RCS which can be subjected to large thermal stresses induced by leaking valves and that were not evaluated in the design analysis of the piping.
Mi thin these systems, a thermal and stress review is performed, and d:cemented in this attachment, to identify the locations of maximum potential stress for nondestructive examination.
- a. The base line temperature (no leakage flow) of the unisolable piping is defined based on piping layout.
The base line temperature in the dead leg (no leakage flow) for a well insulated pipe can be represented by the conduction and/or fre'e c:nvection relationship: Tx -'o > exp [ - (UP/keffA) x] 0 where 'x ~ axial position from hot fluid source T(x) < temperature at axial position x T
- ambient temperature k
ff ~ effective thermal conductivity (e.g. E.R.G. E cert, Heat and Pass Transfer, McGraw-Hill, 1959, fo. free convection) U ~ net thermal resistance between fluid and ambient N14S/042Q4:10 13 ss4PT-SSAD 701i her. 0 P
- pipe wetted perimeter A
- cr oss-sectional flow Base line temperatures are calculated for several nominal pipe sizes, schedule 160 wall and 2-inch calcium silicate insulation, with a 100 degree F ambient temperature.
Free convection and conduction are shown separately in figure 2-1 for 3" NPS and smaller piping. The free convection curves would apply to vertical legs with the hot fluid source at the bottom. The molecular conduction curves would apply to vertical legs with the hot fluid source at the top ("cold trap") or horizontal legs.
- b. The leakage flow is conservatively assumed to be at ambient temperature.
For a small leakage flow into a pipe with stagnant water, the axial temperature can be estimated by the relationship: 'Tx -'o
- exp [ -
c (UP/mCp) x ] 0 where m
- leakage mass flow rate C
- fluid specific heat This estimate shows that for small leakage (.01 gpm) the leakage flow temperature will tend to decrease to close tc ariient temperature over a length of approximately 10 feet. lt is therefor e conservative to assume that the leakage flow is at ambient.
)121 ~ 'OliSN:10 14 SHCT-sslo-7$ 1i Itic. e
- c. The leakage flow is conservatively assumed to stratify and no: aix with the hot dead leg fluid, except in vertical segments of pipe.
The stratification was confirmed from plant measurements of leakage flow and can be expected based on low flow rates (large Richardson number).
- d. Pipe sections of maximum temperature gradient (top to bottom) and temperature fluctuations (cycling of leakage flow) are determ=.ned.
- e. Within pipe sections locations of largest stress concentratio-. are identified for non-destructive examination.
2.0 RESULTS OF ASSESSMENT FOR INSPECTION LOCATIONS 8ased on the methodology described above, the locations of maximun potential hT and most susceptible to fatigue are identified in figures A th.-ough D. These locations are recoaeended for NOE per Bulletin 88-08. Relevant details on selection of location pertaining to the identified system are .rovided below. Per supplement 1 of Sulletin 88-08 the component of maxim~ antici-pated fatigue loadings is selected for base metal evaluation. Ot-erwise, only weld locations are specified as the stress concentration at these po'.nts will generally maximize the fatigue affects. The welds of the reactor coolant loop nozzle do not require inspe:tion due to sufficient mixing resulting from flow in the main coolant piping.
- a. Auxiliary Spray Line, Unit 3 The welds and comporents in the vicinity of the 2 inch branch connection to the main sprayline are recommended for inspection as shown in figure A.
The base metal in the main spray piping near the branch outle: is also recommended for inspection due to the potential for leakage inpingement on this component during lcw spray flow conditions. Also, the weld at the outlet of valve 3-313 requires inspection due to the high dT :etermined for this point. N14s/N!SN:10 15 Ap Iih 4 ~ I " ~ " " + %V " 9 'I WVf ~ ~ "Jl I'. I **-0 0
- K 'PK IW-d
( 0 ~ SEw'-SSAO-7$ 'li hev. 0
- b. Auxiliary Spray Line, Unit 4 The 2" weld on the 4" x 4" x 2" reducing tee at the main sprayline connec-tion is recommended for inspection as shown in figure B. The tee base metal is also recommended for inspection due to the potential for leakage impingement on this component during low spray flow ccnditions. Also, the weld at the outlet of valve 4-313 requires inspection due to the high dT determined for this point.
- c. Charging Pump to C Hot Leg, Unit 3 The base metal and welds of the first elbow downstream of check valve 3-312B are recommended for inspection as shown in figure C.
- d. Charging Pump to C Hot Leg, Unit 4 All welds from the third to fourth elbow down stream of check valve 4-312B (4 weld locations) and the base metal of the fourth elbow downstream of check valve 4-312B are recommended for inspection as shown in figure D.
16 FICURE 2-1 1I.O CON DUGTlON FRED CONVECTKN FOR HPS 3" AND QNLLER 0.8 0 t C3 I 0 0.4 I 0.2 0.0 0 DISTANCE'FROM HOT LEG, (FT) EFFECT OF MOLECULAR CONDUCTION AND FREE CONVECTION ON AXIAL TEMPERATURE DISTRIBUTION 311$ o/042248 lO SE&PT-SSA:-1814 Rev. 0 ATTACSIENT 3 INSPECTION GUIOEL INES Based on the examinations performed at Farley Unit 2 on the sfx(6) inch schedule 160 safety injection lines, the following supplemental examfnatfo..s were able to detect the through-wall indication in the Farley Unit 2 line. Perform penetrant examinations of N5 of the outside diameter weld surface plus 1/2 inch on each side of the above welds where practical. If UT is performed, the following guidelines shall aoplv to account for Bulletin 88-08 Supplement 2: Performing a 45 degree refracted shear wave examination using a 2.25 H.:z 0.5 to 0.25 inch diameter transducar, calibrating out to a one and one-half vee exam for all of the above welds. Performing an additional 60 degree refracted shear wave examination using e a 0.50 to 0.25 inch diameter, 1.5 MHz transducer, calibrating out to a one and one-half vee exam for all of the above welds. Scanning sensitivities should be at 14 dB above reference sensitivity with a noise level of less than 1Ã full screen height for the 45 and -:C degree exams. If the noise level exceeds the above limit, reduce the scanning sensitfvity in one dB fncrements until the noise level drops .o below the above level, and record this reduction on the applicable da~ sheet. Record and evaluate all indications that traveled fn time, are not attributed to component geometry and have an amplitude of greater tha; c-equal to 20K of the distance aaqlf tude correction curved. > SolOI 1%410 18 FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE B~ZNATZONS OF UNZSPLABLB PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS BFFECTS RBFERBNCB NRC BULLBTZH NO ~ 88 08 APPBNDZX M NRC BULLETIN NO ~ 88 08 NRC BULLETIN NO. 88-08 THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS 30 0
- t gl lg '
/ P $g 5' g @gal jap gQ Q tt ), VO, l 'W I'h g', gRQA OHB No.: 31SD-QDll NRCB 88-08 UNITED STATES NUCLEAR RFGULATORY COMMISSION OFFICE OF NUCLFAR REACTOR REGULATION WASHINGTON, O.C. ZC555 June 22, 1988 NRC BULLETIN NO. 88-08: THERMAL STRKSSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS Addressees: Dll holders of opcratfng lfcenscs or constructfon permfts for lfght-water-cooled nuclear power reactors. Puruase: The purpose of thfs bullctfn fs to request that lfcensees (1) rcvfcw theft reactor coolant systeas (RCSs) to fdentffy any connected, unfsolable pfpfng t that could be sub)ected to temperature dfstrfbutfons whfch would result fn unacceptable therma) stresses and (2) take actfon, where such pfpfno fs fdentfffcd, to ensure that the pfpfng wfll not be sub)ected to unacccptablc thermal stresses. Ocscrf tfon of Cfrcumstances: On Occcmber 9, 1987, whfle Farley 2 was operatfng at 33 percent power, the Ifccnsce noted fnc~ased mofsture and radfoactfvfty wfthfn contafnment. TI:c unfdentfffcd leak rate was determfned to be 0.7 gpe. The source of leakage was a cfrcumferentfal crack extendfng through the wall of a short, untsolable scctfon of emergency core coolfng system (KCCS) pfpfng that fs connected to the cold lcg of loop B fn the RCS. Thts sectfon of pfpfng, consfstfng of a nozzle, two pfpe spools, an elbe', and a check valve, fs shown fn Ffgurc 1. The crack resulted fr+ hfgh-cycle thermal fatfgue that was caused by rcla-tf vcly cold water lcakfng through a closed globe valve at a pressure sufffcf cnt to open the check valve. The leakfng globe valve fs fn the bypass pfpe around the boron fngectfon tank (BIT) as shown fn Ffgure 2. Durfng normal operatfon thfs valve and others fsolate the KCCS pfpfng free the dfscharge pressure of the chargfng poaps. 0th a chargfng pump runnfng and the valve leakfng, temperature stratfffcatfon occurred fn the ECR pfpe as fndfcated fn Ffgure J. In addftfon, teaperature fluctuatfons were found at the locatfon'f the faf lcd weld wfth peak-to-peak plftudes as large as 70 degrees F and wfth perfods between 2 and 20 mfnutes. The staff has learned recently of a problem dfscovered at Trojan fn the pressur-fzer surge lfne whfch fnvolved cxcessfve stresses due to thermal stratfffcatfon. The staff belfevcs that coarsen elements may exfst between the Farley 2 cvcnt whfch necessftated thfs bulletfn and the observatfons at Trojan. The need for an addftfonal generfc cawunfcatfon fs befng consfdercd as part of our ongofng cvaluatfon of the Trojan event. 8806170291 4 / NRCB 88-08 June 22, 1988 Page 2 of 4 Discussion: used for charging the RCS wfth coo the chemfcal and volume control system durfng normal operatfon and fnfectfng emergency core coolant at high pressure durfng a loss-of-coolant accident (LOCA>. Separate runs of piping from these pumps are connected to separate nozzles on the RCS pfping for norma> charging 1'Iow, backup charging flow, and'hot- and cold-leg KCCS fnjectfon and to a nozzle on the pressurizer ~or auxiliary pres-surfzer spray. All of these runs of pfpfng, downstream from the last check valve. in each pipe, are susceptible to the kfnd of failure that occurred in the ECCS piping connected to the cold Ieg of loop B. ln any light-water-cooled power reactor, thermal fatfgue of unfsolable pfpfng connected to the RCS can occur when the connected pfpfng fs isolated by a leaking block valve, the pressure upstream from the block valve is higher than RCS pressure, and the temperature upstream is signfffcantly cooler than RCS temperature. Because valves often leak, an unrecognized phenomenon and possfbly unanalyzed condition may exist for those reactors that can be sub)ected tn these condftfons. Under these 'conditions, thermal fatigue of the unfsolable piping can result fn crack fn1tfat1on as experienced at Farley 2. Crackfng has occurred at other plants in Class 2 systems (see IE Bulletfn 74-13, "Crackfnj -'n Feedwater System Piping," dated June 25, 1979 and Revfsfons 1 and 2 dated August 30 and October '.5, 1979, respectfve1y). Subgectfng flawed pfpfng to excessfve stresses induced by a seismic event, waterhaaer.r, or sone other cause conceivably could result fn failure of the pipe. General Oesfgn Crfterfon 14 of Appendix A to Part 50 of Title 1l'f the Code of Federal Regulations requires that the reactor coolant pressure boundary be des1gned so as to have an extreneIy low probabflfty oi'bnormal leakage, o. rapidly propagating faflure, and of gross rupture. At Farley 2, the pressure boundary failed well wfthfn fts design life. ~Af I Rcvfew systems connected to the RCS to determine whether unfsolable sections of piping connected to the RCS can be subjected to stresses from temperature stratfffcatfnn or temperature oscfllatfons that could be fnduced by leaking valves and that were not evaluated fn the h.sfgn analysfs of the pfping. For those addressees who determine that there are no unfsolable sections of piping that can be subjected to such stresses, no addftfonal actions are requested except for the report requfred below.
- 2. For any unfsolable sectfons of piping connected to the RCS that may have been subjected to excessive thermal stresses, examfne nondestructively the welds, heat-affected zones and hfgh stress Iocatfons, including geometrfc d1scontfnuftfes, fn that piping to provide assurance that there are no exfstfng flaws.
J 'AO,h\ w hJ)$ 1>%iJg~t7~$ ;,pgv ~ > rp tlW~et 9e'PP .h,~ I ., ~ +f eh<'/ (r ws ~, e+ Q>> V>>>Q p QW,, sag,, \ . %vw 'lW<'P' 5 1 of pr, y+gpl(e~ 1 ew\I g~v 1'PCS 88-n8 "une 22, 1988 Page 3 os 4
- 3. plm and fmplement a program to provide continuing assurance chat unfsolabIe sectfons of all piping connected to the RCS wfll not be sub)ected co com-bfned cyclfc and statfc thermal and other stresses thaC cauld cause ~atfgue faf lure durfng the remafnfng life of the unit. Thfs assurance may be prn-vfded by (1) redesfgnfng and modffyfng these sections oi'fpfng Co wf Chstand combfned stresses caused by varfous loads fncludfng temporal ar d saatfaI dfstrfbutfons ot'emperature resulting from leakage across valve seats, (2) instrumentfng this piping to detect adverse temperature dfstrfbutfons and establishfng approprfate Ifmfts on Cemperature dfstrfbutfons, or !3) provfdfng means for ensurfng that pressure upstream from block valves whfch might leak fs monitored and does not exceed RCS pressure.
For operating plants 'not in extended outages, Action 1 should be completed within 60 days of recefpt of'his bulletin, and Actfons " and 3, i~ required, should be completed before the end of the next refueling outage. If the next refuelfng outage ends within 90 days after receipt of thfs bullctfn, then Actions 2 and 3 may be completed before the end of the followfng re-fuelfng outage. For operatfng plants in extended outages and f'r plants under constWctfon, Actfon 1 should be completed within 60 days of receipt of Chfs bulletin or before achfevfng crftfcalfty, whichever fs later, and Actfons 2 and 3 should be completed before achfevfng crftfcalfCy, unless crfticalfty fs scheduled to occur-wfthfn 90 days of receipt of thfs bulletin. In chat case, Actions 2 and 3 should be ctxwpleted before the end of the next ac-t'uelfng outage. Re ortfn R ufrements: 1 0 ~ Mfthfn 30 days of completfon of Action 1; each addressee shall submit a >etter conffrmfng Chat the actfon has been completed and descrfbfng Che results oi'he revfew. If the review performed under Actfon 1 indicate. that a potential problem exists, the conf'frmatory letter shall fnclude ~ schedule for completfng Actfons 2 and 3.
- 2. Those addressees who determfne that there are unfsolable sectfons oi- -.
that can be subjected to stresses i'rom temperature stratfi'fcatfon or c~ ature oscillatfons that could be induced by leaking valves and Chat wer not evaluated fn the desfgn analysfs of Che pfpfng shall subnft a Iec e. wfthfn 30 days of coepletfon of Actfons P and 3. This letter should cor Chat Actfons 2 and 3 have been completed and describe the actfons taken. The wrftten reports, requfred above, shall be addressed to the U.S. nuclear Regulatory Camfssfon, ATTN: Document Control Desk, washington, D.C. 20555, u der oath or afffrmatfon under Che provfsfons of Sectfon 18."a,'Atomic Eneray ct of 1954, as amended. In addftfon, a copy shall be submitte.d to the appro-prfate Regional Administrator. 4 I Yi I t, y <A /j W % t, )(' ~' et' NRCB 88 08 Dune 22, 1988 Page 4 of 4 This requfr~nt for fnformat$ on was approved by the Offfce oof Mana ement and anagement Budget under clearance number 3150-0011. If you.have any ouest1ons regarding thfs matter, please contact one of the n s ra or.o f the technical contacts listed below or the Regional Administrator. h appropriate 'NRC regional office. ..'w~~> ~ 48<-~.~ Charles E. Ross), Okrector Pfv)sfon of Operational Events Assessment Office of Nuclear Reactor Regulation Technical Contacts: Roger M. woodruff, NRR (301) 492-1180 Pao Kuo, NRR (301) 492-0907 Attachments:
- 1. figure - Farley Temperature Oata e
1 2
- 2. Ffgure 2 - Farley 2 ECCS
- 3. l.1st of Recently Issued NRC Bul?et$ ns
h 8t t %pe tp'l =p, If@, 'Fpl I c y ~ J' >> ~>> WllH INTHOLIT LEANAGE LEAKAGE TOP Gf FQ% 448f 4%f IOflONOf tltf RNf 4$ % FAREO WKLY ICS COLO LE4 ~ ~ y IFARLKY2 TEMPERATURE DATA 4 ) g % I l" '," ' + E q t', l 4 ~ > I 'p, 8','.% 8 "/'k< ) $$ pl 7f'6+~ >> W f% +Mt'ltp)tCIQ KCCS YO hCS COLO LKOS QOhNAL CHAholgo vo ace coen uo e CHASQNONgg4 thESSURK SARgy NUKClNNtulip It I ' 'tt t " 't+ - 'p ' 8, JQCPt f ',: lf 0 ~ tP ' 7 tt'tt%, P g