Text

Rev 0 to Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant Unit 3
	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: L-90-226, Forwards Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects for Turkey Point Nuclear Power Plant, Per NRC Bulletin 88-008; ML17348A320;
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)
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0 JUNO NUCLEAR ENGINEERING EQUIPMENT SUPPORT

& INSPECTIONS GROUP 700 Universe Blvd.

Juno Beach, 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+

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BOX 3088 FLORIDA CITY'LORIDA 33034 COMMERCIAL SERVlCE DATE 14 DECEMBER 1972 NRC DOCKET NUMBER:

DOCUMENT NUMBER REVISION NO ~ :

50-250 ESIG-PTN-88-08 REV.

0 DATE: 05/22/90 PREPARED BY:

Sr. Specialist ISI DATE /

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1 TABLE OF CONTENTS.

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6 ABBREVIATIONS........................................

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1.0 INTRODUCTION

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PROGRAM APPLICABILITY.~ ~ ~......

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1.2 INSPECTION INTERVAL...........................

1.3 INSPECTION PERZODS ~ ~ ~ ~..

1o4 APPLICABLE DOCUMENTS ~ ~ ~ ~ ~ ~ ~ ~ ~......

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1.5 APPLICABLE CODE EDITIONS AND ADDENDA..... ~ ~ ~..

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ENGINEERING RECOMMENDATIONS ~ ~ ~ ~....

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10 2.1 CHARGING PUMP TO PRESSURIZER AUXILIARYSPRAY LINE ~ ~ ~ ~ ~ ~ ~ ~ ~

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CHARGING PUMP TO "C" HOT LEG..

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10 3.0 ABSTRACT OF EXAMINATIONS PERFORMED.......

11 3.1 APPLICABLE AREAS............

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11 3.1.1 AUXILIARYSPRAY LINE..................

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11 3 '

ULTRASONIC EXAMINATIONS.................-..

11 4.0 ABSTRACT OF CONDITIONS NOTED.....................

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4.2 CHARGING LINE.....

12 4.2.1 3"-CH-1301-42.........................

12 4.2.2 3"-CH-1301-43.........................

12 5.0 CORRECTIVE ACTIONS TAKEN AND/OR RECOMMENDED......

13 6.0 EVALUATIONCRITERIA.............................

14 6 ~ 1 CLASS 1 ~

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6. 1. 1 ACCEPTANCE STANDARDS FOR CLASS 1......

14 7.0 INSERVICE INSPECTION

SUMMARY

TABLES.............

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7.1 DESCRIPTION

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SUMMARY

PLAN TABLES EXPLANATIONS..... ~

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~ 1 GENERAL. ~......

~ ~ ~ ~ ~.

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INSERVICE INSPECTION

SUMMARY

REPORTS'

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16 16 8.3 SPECIAL REPORT........

'6 APPENDXCES A

REFERENCE DRAWINGS...............................

17 B

PERSONNEL CERTIFXCATIONS ~ ~ ~ ~...

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C ULTRASONIC EQUIPMENT. ~..

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D ULTRASONIC TRANSDUCERS

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ULTRASONIC COUPLANT. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

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THERMOMETERS ~ ~

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LIQUID PENETRANT MATERIALS~ ~.....................

H EXAMINATIONPROCEDURES I

ULTRASONIC CALXBRATION BLOCKS J

LIQUID PENETRANT DOCUMENTATION DATA PACKAGES K

ULTRASONIC DOCUMENTATION DATA PACKAGES.....

23 26

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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 NUMBER DESCRIPTION OF REVISION REASON FOR THE CHANGE DATE REVISED APPROVALS

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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.

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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 B&PV C&P CH ESIG FP&L ISI AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE CODES AND PROGRAMS GROUP CHARGING EQUIPMENT SUPPORT

& INSPECTIONS GROUP FLORIDA POWER AND LIGHT COMPANY INSERVICE INSPECTION JUNO NUCLEAR ENERGY SERVICES NDE PTN-3 RCS RC MATERIALS, CODES AND INSPECTIONS SECTION NONDESTRUCTIVE EXAMINATION NUCLEAR REGULATORY COMMISSION TUEKEY POINT PLANT UNIT NO.

3 MAIN REACTOR COOLANT SYSTEM REACTOR COOLANT I

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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 NOTE:

February 22, 1984 September 21, 1987 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 1.4 APPLICABLE DOCUMENTS February 21, 1994 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 ASME BOILER AND PRESSURE VESSEL CODE g SECTION XIg 198 0 EDITION THROUGH THE WINTER 198 1 ADDENDAg RULES FOR ZNSERVZCE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS" ej U.

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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 AUXILIARYSPRAY 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.

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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 AUXILIARYSPRAY 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.

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3 examination activity:

4.1 AUXILIARYSPRAY 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.

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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.

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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.

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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.

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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

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TURKEY POIHT NUCLEAR PLANT UNIT 3 INSERVICE INSPECTIOH SPECIAL REPORT SECOND INTERVAL, SECOND PERIOD, SECOND OUTAGE (1990)

CLASS 1

COHPLETED COHPONENTS PAGE'5 A ZONE NUNBER: 035 SUNHARY EXAHINATIOH AREA HUNBER IDEHTIFICATIOH ASHE SEC. XI CAT0Y EXAII ITEH HO HETHOD PROCEDURE N I S

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C UT 70 NDE 5.19-1 UT-45 NDE 5.19 1

C 2 16 90 PT EXAH CONPLETE C

2-16 90 UT 70 DEGREE AXIAL O.D.

GEONETRY 2 16 90 UT 45 DEGREE AXIAL SCAN COHPLETE

UT-54**

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C PIPE - TO - VALVE (3 313) 89.40 UT 45 NDE 5,19 2 UT 70 HDE 5'9-3 C

2-16.90 PT EXAII COHPLETE C

2 16 90 UT 45 DEGREE LINITED TO.3" FROM US SIDE TOE OF HELD 8 0"-1" CM AHD 0".'I" CCH.

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TRO TURKEY POIHT NUCLEAR PLANT UNIT 3 INSERVICE IHSPECTIOH SPECIAL REPORT SECOND INTERVAL, SECOND PERIM, SECOND OUTAGE CLASS 1

COHPLETED COHPONEHTS N

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ZONE NUHBER: 045 SUHHARY EXAIIIHATIOH AREA NUHBER IDENTIFICATION ASHE SEC. XI CATGY EXAII ITEH NO HETHOD PROCEDURE N I 8

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C UT 45 NDE 5.4 44 UT 60 HDE 5.4-44 2-23-90 PT COHPLETE 2 24-90 UT 45 COHPLETE 2 24 90 UT 60 COHPLETE

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155400 3".CH.1301.43 ELBOH TO - PIPE 8-J PT 89.21 UT 45 UT 60 HDE 3.3-233 C

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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 will be developed and maintained in accordance with IWA-6000 of 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.

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003-A31 003-A44 TITLE 2" AUXILIARYSPRAY LINE 3" CHARGING LINE 17

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~ 3-SR-43 FLOW /

L CONSTANT WEIGHT HANGER 3-SR-49 QA U-BOLT RESTRAINT

~ 3-RS-I U-BOLT RES1RAINT

~ 3-RS-2 PEN. B 32 45m 3 -CH-1301 CHARGING CONT. ON f)2 DWG. 003-A44

/

ZONE 045 3

VCH 118C 22 21 BOX RESTRAINT 2 -RO-1210~

,2 20 16 17 MECHANICAL SNUBBER ~i) 3-SR-47-B tx BOX RESTRAINT 3-SR-65 SA MECHANICAL SNUBBER lll-~ 3-SR-47-C

+2 XO REO.

MECHANICAL SNUBBER

~ 3-PS-592 7 45m HQK5'YSTEM IO: 041 6c 047 CVCS STRESS PROBLEM: PS-I/023 SPEC NO:

2 -RC-2501R-5 19

~EL. 22 -0 U-BOLT dc ROO HANGER 3-HCR-A SPRING HANGER 3-SR-46 SPRING HANGER 3-SR-45 ~

11 12'3 45'H

~fLOW PA 10 7

MECHANICAL SNUBBER

~ 3-SR-47-A RIGID TELESCOPING STRUT 3-HGR-C REFERENCE DRAWINGS 5177-102-SK-P-641 REV. D 5177-102-SK-P-639 REV. D 5610-FSK-M-433 5610-M-410-202 SHT. 2 OF 2 5610-M-420-214 SHT. 3 OF 3 5613-P-661-S REV. I SHT. 2/4 DESIGN PSIG: 2485 OPERATING PSIG: 2335 HYDROSTATIC PSIG: 2624 TEMP(F): 650 TEMP(F): 493 TEMP(F): 547 PRESSURE dc TEMPERATURE STATS 2

160 3/4 160 A376 TP316 SMLS A376,TP316 SMLS UT CAUBRATION BLOCK:

N/A MATERIAL SPECS SIZE SCH TYPE DATE: 10-20-89 REVISION APPROVED BY:

4

, L. ANDERSON ZONE: 035 DRAWING NUMBER:

003-A31 CODES dc PROGRAMS GROUP TURKEY POINT UNIT 3 TITLE:

2 INCH AUXILIARYSPRAY UNE TO PRESSURIZER

~

~ t ".I g ~

7 I> ~

w rg> r<< ~

e iS...

w e 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-118A 3-VCH-130 RIGID ROD HANGER ANNULUS SIDE BIO SHIELD 45~

WALL 33+34 4

30 PEN. A~

REACTOR SIDE SPRING SUPPORT 3-SR-38 SPRING HANGER 3-VCH-114 29 -RCS-1308 MAIN REACTOR COOLANT CONT. ON OWG. 003-A08 ZONE 014 45 EL 25'-7 1

2 ROD HANGER 3-VCH-131 39 36

/

~<o6, BOX RESTRAINTi 3-SR-39 40 44 ROO HANGER 3-VCH-132 4

43 042 L. 23'-9 7 8-3-31 28 3/4 12 I

BOX RESTRAINT 3-PS-60 13 45%

14 3/4 ANNULUS SIDE BIO 10 SHIELD WALL 9

8 7%

4W PEN. NO. 2~

RIGID TELESCOPING STRUT 3"-CH-1301 0

QB HQKS'YSTEM: 047 STRESS PROBLEM: PS-I/023 SPEC NO.: 3"-CH-2501R 5610-M-420-3 SHT. 3 5610-M-410-91 SHT. 2 5613-P-661-S REV. 0 SHT 1 IL 2 OF 4 23 CV-3-311 24 2 X3 RED.

I 2 -RC-1310 AUX. SPRAY CONT. ON DWG. 003-A31 ZONE 035 22 21 QA 15 16 18 CV-3-310A ~17 3 -CH-130 I

CHARGING CONT. ON DWG. 003-A45 I'ONE 046 WELDED SUPPORT 3-VCH-115 k

SPRING SUPPORT

~ 3-SR-64 26 PB ~ CV-3-3108 2g 45'8 PIPE SUPPORT

~

3-SR-37 REACTOR 45'EGENERATIVE HEAT EXCHANGER CONT. ON DWG. 003-Vl1 ZONE 05g O

EL 15'-6" 1

STANCHION REFERENCE DRAWINGS 5177-SK-P-639 REV. C 5177-SK-P-642 REV. 0 56'Io-M-420-214 SHT. 3 OF 3 E2387-1C-297 5610-T-E-4505 SHT.

1 5610-T-E-4501 SHT.

1 PRESSURE Ec TEMPERATURE STATS DESIGN PSIG: 2485 TEMP(F): 680 OPERATING PSIG: 2235 TEMP(F): 653 HYDROSTATIC PSIG: 2335 TEMP(F): 547 160 A376 TP316 SMLS UT CALIBRATION BLOCK:

N/A MATERIAL SPECS SIZE SCH TYPE TITLE:

3 INCH CHARGING LINE FROM RHX TO LOOP C

HOT LEG DATE: 10-19-89 REVISION APPROVED BY:

4 E. L ANDERSON ZONE: 045 DRAWING NUMBER:

003-A44 pp) Qe CODES dc PROGRAMS GROUP TURKEY POINT UNIT 3

+'})6 I 4

~ ~

- 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

CARR, FRANCIS T.

BRANNIN, MICHAEL KOVALOVICH, PAUL REDDING, CRIS ROBBINS I MICHAEL D VANO, RICHARD J.

VT-1 VT-2 VT-3 VT-4 UT PT MT EYE EXAM, N/A N/A N/A N/A IIIIIIIII 04-14-89 N/A N/A N/A N/A IT IT N/A 09-08-89 II N/A N/A N/A II II II 01-05-90 N/A N/A N/A N/A II II II 02-02-90 II II II II II II II 08-09-89 N/A N/A N/A N/A IT IT IT 09-11-89 18

JNS+I -9. 3 Revisi IVE HRHINATICN PEBSGNNEL CZRFIFIGG'ICN NhbR F. T. Carr IZNYIBlaSIINIZVHr.

EQQHINATICN b%?MD Liquid Penetrant LIMITATIQ6 HQHINATI(ÃREKKiIS:

BASIW 80%

(tenSm} GENERAL 808 SPECIFIC 95%

mCrlCAL 100~

PCS ITE 88.7SS AIMINISIKHEDBY~ (~ 718}

11/87 AQHINIS'IIHBZIBY~ <~

I

'WIR ~

AIMINISYIHIHD BY Hellier Associates DARB 1/88 ADBINISIBISB)BY Hellie M~~

OVIR I/88 (AVIRAGE CP ALL SK883)

LEVEL III CNLY mmmrmx:

(INVEIGLE CHmamICAL adam) lÃIKS NB. ADS.'IBIS SRIKO 12/80-Present 86 3/75-11/80 FPL; Level ZII, 1KB Engr., respansible for ZSX eeaminatian procedures and technical perfoaaance of nuclear a fossil NDE activities.

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 respans e or g Sect~ Mrg NDE Product~

and technique development.

10/70-2/74 40 Seatrain Shi.

g Mgr. QC 5 HOT Depte respans or cxmp te mspectian of super tanker CERTIFIED BY (see attached resum. for additianal infarmatian}

TITLEV.P. Nuc. Cyexatians

~TE ~p $6 4c

'IBIS CZRI'IFICATICN IS VALIDQTFIL 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 HQMNATICNPEISC5NEL (XRFIFICATICÃ

?ybR Frank T. Carr QRCIPIGQ'ICSI LIMIL CZZ KNMINATICNbRBKD Ma etic Partic1e LIMITATICM None EQMINATICNHRSIEH c BAS IC<<

SPECIFIC

'PRACTICAL CC5%'C6 ITE 80'8 96%

100%

89%

AIMNIFIKREDBY~

(QA-718)

D'YE U/87 AIMNIFIKKOBY ASAP JA-718 BASE 11/87 ACMINIBIIDIBDBY BeUAes AsseessSes BASE 1/88 AIÃINIPIEFSSD BY Helliez Assccistes DIIE 1/88 (AVZmt:a Ce ALL SCam)

<<LEVEL III C5LY PPL. Level III, NDE Engr.

respmsibie for ISI examination and technical perfozmance of nuclear

& fossil NGE activities.

e EfHREBKZ:

( INVERSE CHRCSMGICAL CBKHt)

CRIES NS. AEB.'IHIB SECIYSS

. CBPANY (IIKLUXYYSB CF SCSK AND MX IZVBL) 12/80-Pzesene 86 3/75-11/80 3/74-12/74 10/70-2/74 68 10 40 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.

Offslxam Power stems. Sect~ Mgr. NDB Production e

r ard tedmuye dee3xgnmt.

Seatr;Lin Shi

Hgr.

QC & NOT Dept.

ccats ete ~pect~ of super tanker CENIIFIZD BY

/ 4 ENTITLE Nu 0 r tf n WE 4-J4-

nager, MCI

'IHIS CZRFIFICATICN IS VALIDMFIL "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 EXAMINATEPEISCINEL CZRPIF ICATKH F. T. Carr EXAMINATICNbRIKD LIMITATIQ6 None EXAMINATKNRHSUGIS:

Ultrasonh c CZRnFlmV1m LEVEL III

{3ASICS'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 Isr Assecf aces MIK I/88 CRXQS ITE

82. 25K (AVERAGE CP ALL SCRIBES) tLEVEL III CNLY BAKE IO. sES.'IHIS 'ARIIIXI 12/80-Present 86 FPL; Level III, NDE Engr. respons)ble for ISI examination procedures and technical performance of nuclear d fossil NDE act$ vft$es.

Nuclear Ener Svs; Dfrector ISI Eng., Level III respons e for I examinatfon procedures, techniqul development, technical d)rection of field NDE exam$ natfon act$ v$ t$ es.

0ffshore Power S stems; Sect)on Mgr. NDE Production respons e for procedure and technique development.

Seatra)n Sh) build)n Co Mgr. gC 5 NDT Dept.

respons e for comp ete nspect1on of super tanker construction.

3/75-11/80 68 3/74-12/74 10/70-2/74 10 EPERIBKE:

( INVERSE CHRQKGX'rICAL CRIER)

Q5PANY ( INCLUX TYPE CF MXK AND NDE IZlfEL)'See attached resume for add)tional

$nformatfon)

CENTI IFIZD BY /

Air TITLE V.P. Nuc. Operations RTE p-/4-REV IEWEO BY nager.

MCI

'IBIS CZHTIFIC'ATICN IS VALIDQFIL "All historical information supplied by me to ccayi this certification is true and correct to the best of my knowledge" te a

/ EEAMINEE

F. T.

CARR NOE S ec1alist - Nuclear Ener Services REVi 4/84 West Yirginia Inst1tute of Technology, Engineering and Business Administration 1965 - 1970 1970 1970 - 1974 1974 - 1975 1975 - 1981 Oouglas Ultrasonics, Inc., Ultrasonic Technician with varied independent assignments worldwide.

A.J. Testing Laborator1es, NOT Technician and Ultrasonic Speci al 1 st.

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.

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.

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 SUBJECT W.

Va'. Inst. of Tech Branson Instruments Krautkramer Ultrasonics Krautkramer Ultrasonics Mont e

WV St d

Richmond VA Norwich CT Stratford CT 61 5/69 24 hrs 10/69 40 hrs 2 68 40 hrs Basic U

MT/PT/RT UT ET 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 Kean College Chicago, IL Union,,N.J.

1973 40 hrs 1973 32 hrs UT/RT/MT/PT UT/RT/MT/PT/ET Kean College Union, N.J.

ASNT National Conference

'leveland, OH 1973 1974 40 >rs 32 hrs Radiography (Level IE)

Ultrasonics

'SNT Nat iona 1 Conference Battelle-Columbus Labs Houston'X

Columbus, QH 1976 2/78 32 hrs 40 hrs Ultrasonics Ultrasonics-IGSCC Workshop ASNT National Conference ASNT ZETEC EPRI Atlant,

GA

Atlanta, CA Miami, PL i Charlotte,'C 1981 10/81 5/82 32 hrs 8 hrs 40 hrs.

/84 40 hrs UT/RT/MT Leak Testing Eddy Current UT-Pled Sizing

~Iooe ~Q'b t

INSPECTION PERSONNEL EYE EXAMtNATION QAt5~

/~W~

y/ gl j7 ~r)'/)

Lac st i att:

iAST Without Glasses 0

With Glasses FI AST MIOOLE Chart No. J1 Without Glasses gj With G lasses d;.

Chart No. Snellen Right Eye g OK 0

See Recommendation Right Eye 5l'K 0

See Recommendation

',eft Eye df OK

. Eyes OK 0

See Recommendation 0

See Recommendation Left Eye g

OK 0

See Recommendation Both Eyes g OK-, 0 See Recommendation Color Blindness

( 0 Isihara 0 Isochromatic

) - Write in Number Read 1

.,2 3

4 5

6 12

'13 14 15

~ 16 17 18 19 20 21 22 23 24 25 26 30 31 32 33 34 35 38 37 38 Recommendation:

See Physic~an stricted Fail Remarks:

~l /i est Administrator

~/c/-) /

pate applicant's Signature

~

<OTE: THE ABOVE P TAWILLMFET THE SNT-TC-1A/ANSI N45.2.6 REQUIREMENTS LATEST REVISION.

Form 4aoatl,a rNontstockoo) Aev a/at

JNS-QI-9 ~-

Revision NONDESTRUCTIVE EXAMINATIONPERSONNEL CERTIFICATION NAME CRIS M.

REDDING EXAMINATIONMETHOD ULTRASON C LIMITATIONS CONTACT TECHNI UES ONLY EXAMINATIONRESULTS 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 Present 2/87 10/89, 6/85 - 7/86 11/83 1/85 1/77 11/83 32 13 13 60

~F g Level IZ ISZ Technician performing Nuclear Fossil Plant NDE.

EBASCO Services Xnc.; Level ZZ ISI Technician performing PSZ

& ISZ examinations at a variety of assignments.

World ech 'cal Servi es; Level II NDE Technician.

Universal Testin Labs Inc.; Level II NDE Technician.

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 c rtifica is true and correct to the best of my knowledge>>

0 NONDESTRUCTIVE EXAMINATION PERSONNEL CERTIFICATION JNS-QI 9.3 Revision p NAME CRIS M. REDDING EXAMINATIONMETHOD LI UID PENETRANT LIMITATIONS NONE CERTZFZCATZON LEVEL ZI I

-.~PXAMINATZON RESULTS:

BASZC4

~NA ADMINISTERED BY (METHOD4)

GENERAL

~78 ADMINISTERED BY SPECIFIC 90%

ADMINISTERED BY PRACTICAL ~94 ADMX11ZSTERED BY COMPOSITE ~87.3 (AVERAGE OP ALL EXPERZENCEW (INVERSE CHRONOLOGICAL ORDER)

F.

T F. T.

F. T.

SCORES)

DATE CARR DATE ~12 28 89 CARR DATE ~12 28 89 CARR DATE 01I108 90

LEVEL IZZ ONLY DATES NO ~

MOB ~

THZS METHOD COMPANY INCLUDE TYPE OP WORK AND NDE IEVEL 10/89

. resent 2/87 - 10/89 6/85 - 7/86

,11/83 - 1/85 1/77 - 11/83 32 13 13 66

~FP

Level II ISZ Technician performing Nuclear~Fossil Plant NDE.

EBASCO Services Inc.; Level IZ ISZ Technician performing PSZ

& ISI examinations at a variety of assignments.

World Technical Services; Level II NDE Techni ian.

Universal Testin Labs Inc.; Level IZ NDE Technician.

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 true and correct to the best of my knowledge" EXAMINEE tification is

JNS QI 9 ~ 3 Revision +

NONDESTRUCTIVE EXAMINATIONPERSONNEL CERTIFICATION NAME CR S M. REDDING CERTIFICATION LEVEL II EXAMINATIONMETHOD MAGNETIC PARTICLE LIMITATIONS YOKE

& PROD TECHNI UES ONLY I

c'XAMINATZON RESULTS9 BASIC*

~N A ADMINISTERED BY (METEOD+)

GENERAL

~78 ADMZNZSTERED BY "

T SPECZPZC

~88 ADMZNZBTERED BY F. T.

PRACTICAL 1004'DMINZSTERED BY.

F. T.

COMPOSITE ~88.6 (AVERAGE OP ALL SCORES)

DATE CARR DATE

~12.2-?

89 CARR DATE-.~12 -22 89 CARR DATE. ~01 26 90

'LEVEL ZII-ONLY--

EXPERIENCE (INVERSE CHRONOLOGICAL ORDER)

DATES NO ~

MOS ~ THIS METHOD COMPANY INCLUDE TYPE OF WORK AND NDE LEVEL 1 0/89 resent 2/87 - 10/89 6/85 7/86 11/83 - 1/85 1/77 11/83 32 13 13

~FP

Level II ISI Technician performing Nuclear~ Fossil Plant NDE.

EBASCO Services Inc.; Level IZ ISI Technician performing PSI

& ISI examinations at a variety of assignments.

World Technical Services; Level II NDE Technician.

Universal Testin Labs I c.; Level II NDE Technician.

U. S. Steel Cor.; Level II NDE Technician,

Trainee, and Level I covered during this employment.

CERTIFIED BY REVIEWED BY E SUPERVISOR DATE /3n a

TMZS CERTIFICATION ZS VALID UNTIL ~>

0 9+

~'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 LAST n8 CAP FIRST MIOOI.E Lossdon:

Wy S P5 Without Glasses fB With Glasses 0

Chart No. J1 Without Glasses With Glasses

. 0 Q/sl~s Chart No Snellen Right Eye H OK Left Eye 8 OK Both Eyes OK 0

See Recommendation 0

See Recommendation Right Eye 0

OK gY See Recommendation Left Eye 0

OK df See Recommendation Both Eyes Br DK tB Bee Recommendation Color Blindness

( Ktsihara 0 tsochromatic

) - Write in Number Read 0

2 3

4 5

6 7

8 9

10 11 12 13 14 15 16 17 0

18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 Recommendation.'emarks:

Pass QIt/

~see Physician

&Restricted Fail 4d L ~D lS IS ~

I ?

I Irl/rrp ZJC~~ ~ ~-2 W~

r~>dnJ Test Administrator Applicant's Signature m

Date Date tO NOTE: THE ABOVE DATAWILLMEET THE SNT-TC-1A/ANSI N46 2.6 REQUIREMENTS LATEST REVISiON.

forest a302 3,2 tNon Stocitoet) Rev 2rs

CERTIFICATION OF PERSONNEL QUALIFICATION TRAINING SUPPLEMENT SCHOOL (PROGRAM)

LOCATION DATE LENGTH SUBJECT U.

S. Steel Texas

Baytown,

/75 24 hrs.

G.E.D.

Magnetic Particle U.

S. Steel U.

S. Steel EPRI NDE Center EPRI NDE Center EPRI NDE Center EBASCO Services EBASCO Services EBASCO Services EBASCO Services EBASCO Services EBASCO Services EBASCO Services FPI

Baytown, TX

Baytown, TX Charlotte, NC Charlotte, NC Charlotte, NC

Kearny, NJ

Stuart, FL Riviera Bch, F

1980 24 hrs.

1979 40 hrs.

1980 40 hrs.

1978 24 hrs.

1979 24 hrs.

2/84 40 hrs.

7/88 40 hrs.

9/88 32 hrs.

2/87 pf hrs.

2/87

$ hrs.

4/87 Zp hrs.

4/87 5g hrs.

4/87 16 hrs.

4/87 38 hrs.

6/89 80 hrs.

1/90 16 hrs.

llagnetic Pat ticue.

Ultrasonics Level I Ultrasonics Level II Liquid Penetrant Liquid Penetrant UT IGSCC Detection UT IGSCC Sizing UT IGSCC Overlay Radiation Safety Radiography Magnetiw Particle Radiography Liquid Penetrant Ultrasonics AWS Yisual YT-1 thru 4 FPL NDE Procedures

EBASCO SERVICES INCORPORATED Materials Engineering Laboratory. Bldg. 100A Port Kearny. South Kearny, NJ 07032. (201) 344-8400 EBASCO Name: Robbins, Michael D.

CERTIFICATION HISTORY SSN: 408-94-0001 Date Method itr Level 10/05/88 UT-II 10/05/88 MT-II 10/05/88 PT-II 10/05/88 VT-1 II 10/05/88 VT-3&t II 09/12/89 VT<<2 II Basic General 87.50 90.10 76.90 80.00 76.70 93.30 Method S~cific 90.00 90.00 100.0 100.0 95.00 95.00 Specific Practical 97.00 98.00 97.00 86.00 100.0 93.00 Composite 92.05 93.23 91.87 88.40 91.50 93.69 e

EBASCO SERVICES INCORPORATE))

CURRENT NDE CERTIFICATIONS NAME: Robbins, Michael D.

SSN: 408-94-0001 EDUCATION LEVEL: High School METHOD LEVEL RT N/A HOURS OF TRAIN.

MONTHS OF EXPER.

DATE CERTIFIED GENERAL/

BASIC GRADE WT.

SPECIFIC/

METHOD GRADE WT.

PRACTICAL/

SPEC-PRACT.

GRADE MT.

COMPOS.

RECERT.

SCORE DUE CERTIFIER UT II MT II PT II ET N/A VT-1 II 104 24 38 63 164 164 164 132 10/05/88 87.50 0.3 10/05/88 90.10 0.3 10/05/88 76.90 0.3 10/05/88 80.00 0.3 90.00 0.3 97.00 0.4 90.00 0.3 98.00 0.4 100.0 0.3 97.00 0.4 100.0 0.3 86.00 0.4 92.05 08/04/91 R. PAILLAMAN 93.23 08/01/91 H. BULLEN 91.87 08/01/91 H.

SULLEN 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 N/A N/A 63 164 10/05/88 76."70 0.3 95.00 0.3 100.0 0.4 91.50 08/03/91 R. PAILLAMAN 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.

LEVEL III NAME: H.C. Bullen SIGNATURE:

I 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 o E AI I ri'rv c IT I S pe i IfyI GYCRft eye 2 ~

~gt:I e;e D

UNCORRECTED EYEGLASSES 0

CONTACTS 8.

DISTANT VISION ACUITY P

SNELLEN OTHER ISpeciiyt cleft eye

~igITt eye

)RE g UNCORRECTED EYEGLASSES 0

CONTACTS C.

COLOR VISION IS HIHARA 0 OTHER (Specify)

Number of Plates Tested Number of Plates Correctly Read List of Any Plates Read In orrectly NAME OF EXAMINER irrlR LOCATION

~~Ar SIGNATURE 877/

8 TITLE DATE OF EXAM

+ P PART - 8 (To be completed by The Appropriate Level III Individual)

MEETS QA ~ G.3.1 JAEGER J-1 MEETS QA*G.3.1 SNELLEN MINIMUMONE EYE20/40 MEETS QA ~ 6.3.1 COLOR VISION Q

YES Q

NO TEE Q NO Q

N/A Q

YES Q NO' N/A DISCIP EL - III PRINT NAMt SIGNATURE DATE MEETS NDE ~

1 JAEGER J-1 MEETS NDE - 1 SNELLEN MINIMUMONE EYE 20/30 MEETS NDE ~

1 COLOR VISION Q

YES Q

NO

~YES ~

NO P N/A YES Q

NO Q N/A PRINT NAMt i /ffailed. providejusrificarion for waiver of failed condition:

SICNATURt DATE Aprirct' a ~ e Level III s ERE/air EPO CTNI iM ~

MF i

iAi i+Nl/ 'tg

EBASCO SERVlCES tNCORPORATED Materials Engineering Laboratory, Bldg. 100A Port Kearny. South Kearny. NJ 07032, {201) 344-8400 EBASCO Name: Kovalovich, Paul SSN:

050-60-7171 CERTIFICATION HISTORY Date 10/88 10/88 10/88 10/88 Method 6 Level UT-II MT-II PT-II VTl-II Basic General 92.50 83.40 90.00 73.40 Method

~Secific 100.0 80.00 90.00 100.00 Specific Practical 94.00 93.00 93.00 80.00 Camacsite 95.35 86.20 91.20 84.02

I I

o

~ I o

~

I

~

I I

~ I I

II lo I

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'333 5.9 88 EBASCO SERVICES INCORPORATEO REPORT OF EYE EXAMINATlON s A Iti 4 u/gch ohio dd 7i 7/

A. NEAR VISION ACUITY PART - A (To be completed by Eye Examiner)

~ READ JAEGER J-1 0

READ OTHER (Specify)

MLe eye UNCORRECTED 0

EYEGLASSES 0

CONTACTS oo B. DISTANTVISION ACUITY SNELLEN 0

OTHER (Specify)

CVAight eye 0

UNCORRECTED EYEGLASSES 0

CONTACTS 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

/\\ A LOCATION rr'I SIGNATURE TITLE DATE OF EXAM PART - B (To be completed by The Appropriate Level lll Individual)

MEETS QA - G.3.1 JAEGER J-I MEETS QA-G.3.1 SNELLEN MINIMUMONE EYE20/40 MEETS QA ~ G.3.1 COLOR VISION Q

YES Q

NO Q YES Q NO Q

N/A Q vEs Q

No Q N/A DISCIPLINE LEVEL - III hRINT NAMC SIGNATURE DATE MEETS NDE - I JAEGER J-1 QvEs Q No MEETS NDE ~ I SNELLEN MINIMUMONE EYE 20/30 MEETS NDE -

1 COLOR VISION NDE - LEVEL ~ III 'o ci PRINT NAME

'lffailed. provide justification for waiver of failed condition:

SIGNATURE Q vEs Q No Q N/A Q vES Q NO' N/A ApprOpriate LeVel III S ghsiuie shd OsI ~

See reverse side lorinsrrIrerlons.

4' I

'1 0

h'0 PP

'r Iir J r)Q

\\* 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 CERTIFICATION HISTORY SSN:

167-58-4514 Date Basic/

Method Level General Method/

Specific Specific/

Practical Composite 09/08/89 UT 09/11/89 PT 01/18/90 MT 90.00 93.30 75.00 85.00 90.00 95.00 81.00 93.00 92.00 85.80 92.22 86.10

{<<'. (('IF'<<<<'<<'<<0 +0,(

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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 0

READ OTHER (Specify)

IB Left eye

~-1 S Right eye Itr UNCORRECTED 0

EYEGLASSES 0

CONTACTS B. DISTANTVISION ACUITY EV SNELLEN 0

OTHER (Specify) a;...,.

~UNCORRECTED 0

EYEGLASSES 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 LOCATION S a

~

SIGNATURE TITLE DATE OF EXAM PART - B (To be completed by The Appropriate Level ill fndividual)

MEETS QA - G.3.1 JAEG MEETS QA-G.3.1 SNELLEN MINIMUMONE EYE20/40 Q

YES Q

NO QYES QNO Q

N/A MEETS QA - G,3.1 COLOR VISION Q

YES

/A DISCIPLINE LEVEL - III PRINT NAME SIGNATURE DATE MEETS NDE - 1 JAEGER J-1 MEETS NDE - 1 SNELLEN MINIMUMONE EYE 20/30 YES Q

NO Q

YES Q

NO Q N/A MEETS NDE -

1 COLOR VISION

~ES Q NO' N/A I

NDE. LEVEL. III..

r auMZ PRINT NAME

'll'feiled, providejttstift'cation for waiver of failed condition:

SION URE DATE ApprOpriate LeVel III Slpnstllrd end 05I~

Sdd reverse side lorinstfuctions

EBASCO SERVICES INCORPORATED Materials Engineering Laboratory, Bldg. 100A Port Kearny, South Kearny, NJ 07032. (201) 344-8400 EBASCO Name: Michael Brannin SSN; 141-60-0508 CERTIFICATION HISTORY Date Method a Level Basic General 09/08/89 UT I Trainee 90.00 09/08/89 PT I Trainee 86.70 Method

~Seclfic 85.00 85.00 Specific Practical 83.00 97.00 Comcoskte

86. 40

89. 28

EBASCO SERVICES INCORPORATED CURRENT NDE CERTIFICATIONS NAME: Brannin, Michael P

SSN:

141 60 0508 EDUCATION LEVEL: High School METHOD LEVEL HOURS MONTHS OF OF TRAIN. EXPER.

DATE CERTIFIED GENERAL/

BASIC GRADE MT.

SPECIFIC/

METHOD GRADE MT.

PRACTICAL/

SPEC-PRACT.

GRADE WT.

COMPOS.

RECERT.

SCORE DUE CERTIFIER 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 ET N/A VT-1 N/A VT-2 N/A VT-3,4 N/A N/A N/A 16 09/08/89 86.70 0.4 85;00 0.3 97.00 0.3 89.28 09/08/92 H.C. Bullen 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 Q

READ OTHER (Speci(y)

Itr Left eye

~- l 0)v UNCORRECTED Q

EYEGLASSES Q

CONTACTS B. DISTANTVISION ACUITY

~SNELLEN Q

OTHER (Specify) 9YCeft eye

~tght eye NCORRECTED Q

EYEGLASSES Q

CONTACTS 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 LOCATION o

SIGNATURE TITLE 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 MINIMUMONE EYE20/

MEETS QA - G.3.1 COLOR VISION YES Q NO Q

N/A Q

YES Q NO' N/A INE LEVEL - III PRINT NAME EIQNATURE DATE MEETS NDE - 1 JAEGER J 1

MEETS NDE.

1 SNELLEN MINIMUMONE EYE 20/30

~YES Q

NO

~YES I3 No CI N/A MEETS NDE-1 COLOR VISION NDE. LEVEL. III ~f'ds n, rItn~zk.

YES Q

NO Q N/A DATE PRINT NAME

'lffailed, providejusti%'cation for wei ver of feiled condition:

Sl NATURE 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 MODEL NUMBER SERIAL NO PRE OUTAGE LINEARITY POST OUTAGE LINEARITY USL-48 USK-7 USK-7 213222 27276-1078 27276-1091 02/05/90 02/05/90 02/05/90 03/23/90 04/04/90 03/23/90 19 ttf h,

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ULTRASONIC INSTRUMENT.LINEARITYRECORD PROCEDURE CAL-1 INSTRUMENT Model No.

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Frequency Frequency 2a 2 Type CALIBRATIONBLOCK

. ~rr aI Sze~

Straight Beam

( W Sze~

Angle Beam

( erf HORIZONTALLINEARITY VERTICALLINEARITY

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LOW GAIN BACK REFLECTOR

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ACCEPT LIMITS O.

ACTUAL HIGHER SIGNAL 1/2 OF HIGHER ACCEPT.

LIMITSB (CALCULATE)

ACTUAL LOWER SIGNAL 10 10 1.90 - 2.10 2.85 3.15 3.80 -4.20 4.75 ~ 5.25 5.70.8.30 6.65 - 7.35 7.60 ~ 8.40 8.55 ~ 9.46 10 10 IO l

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'Acceptance Limits are 1/2 of the Higher Signal k 5% FSH AMPLITUDECONTROL LINEARITY

~ LOW GAIN HIGH GAIN INITIAL AMPU1UOE

&0% FSH 80% FSH 40% FSH 20% FSH db CHANGE DOWN 6 DOWN 12 UP 6 UP 12 RESULT I.IMIT 32% ~ 48%

16% ~ 24%

ACTUAL HIGHER AIQNAL

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48%

18% - 24%

64% ~ 96%

61%.96%

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ULTRASONIC INSTRUMENT LINEARITYRECORO PROCEDURE CAL-1 INSTRUMENT CALIBRATIONBLOCK Model No.

V TRANSDUCER Serial No.

Brand K

Brand Frequency Frequency Size Q~

Angle Beam

(

)

HOBI2ONTALLINEARITY VERTICALLINEARITY (SIGNALAMPLITUDES IN '%SH)

LOW GAIN BACK REFLECTOR GRIO LOC.

ACCKPT UMITS O.

ACTUAL HIGHER SIGNAL 1/2 OF HIGHER ACCKPT.

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64% - 96%

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ACTUAL HIGHER AlGNAL

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UT Level:

Date:

UI.TRASONIC INSTRUMENT.LINEARITYRECORD PROCEOURE CAL-1 INSTRUMENT M5K.-7 Model No.

TRANSDUCER Serial No.

CALIBRATIONBLOCK z

Brand Brand Frequency Frequency Size

-S 6 Straight Beam Size ~zr Angle Beam i

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16% - 24%

64% - 95%

54% ~ 96%

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16% ~ 24%

64% ~ 98%

81% 96%

10 I

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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 H12310 L23777 GAMMA GAMMA GAMMA MSWS MSWS MSWS

~ 25" 25fl

~ 25"

2. 25 2 ~ 25 2'5 20'

TRhHSDUCER CERTIFIChTIOH

~nsducer Descri tion s/s a

\\

Fr@ agency MHs Sise ~~

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Inspector Date 9-TRJLCC Contact Immersion Honfocused Z

Water Path Spherical J

Cylindrical TRhCK IZ L

itive Sensitivity dB 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 an inconsequential figure.

Tho horisontal calibration for Traco I is the same as that for Trace 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

Re1ative Sensitivity OB gy Setting~~

Impedance SQ.rt.

TRACE Inspector

(

Date Transducer Description ries C TRACE MHz Size~5'o.

~ Contact ~ Immersion ~ Nonfocused Water Path ~ Spherical

~ Cylindrical TRACE Style u.~

Connector ~)

II

%MS>

NL'RNRRRKNS 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 e

~ lay line.

Nonfocused immersion tr ansducers are tested in water over a flat 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 P. 0.

Box 350

~-

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TRANSDUCER CERTIFICATION Transducer Descri tion es SiN B

Prequency

.- ~

HHS Sita ~~

TRACE Contact Immersion Nonfocused I

Spherical r ~

Target

.6 y <

+Cylindrical TRACE IX ative Sensitivity

~

dB Pv5%Ãi'%RR~iiig 5IRWlww Energy Setting M

Impedance ~~ TRACE IIX peak or QCenteo Ptequency e2 3.

HHa Inspector Date Testin Procedure C

D 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 NUMBER MANUFACTURER DESCRIPTION 8330 ECHO LABS ULTRAGEL II 21

~,* *,v v'\\"

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'",e aralarios, Ina r

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Cable Addrotst INTEL Telest I]9187 No.

486170 Oar assay of the salrtple of Ultragel II Technicare-Echo, Incoprorated DATE February 4, 198 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.

To Technicare-Echo, Incorporated Lewistown, Penna.

Sworn to and Subscribed befor me this 4ta day of Feb~;ry-1983.

( r'~e ~7~~.

i>ly Nojary&Gblic Cos"efssioo e

iree Autos't 13, 1984.

INTERNATIONALTESTING LABORATORIES, IY Thc liabilityof 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.

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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 MANUFACTURER SERIAL NUMBER 90-006 PTC INSTRUMENTS MODEL 312F 90-010 PTC INSTRUMENTS MODEL 312F CAL DATE EXPIRATION DATE 01/19/90 04/19/90 01/19/90 04/19/90 22

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TEMPERATURE INDICATOR CHECK RECORD (S/N)Identification CHECK READINGS 50o F

CHECK DATE

-/

d VOID DATE STD.

METER q@0 STD.

HIGH METER SIGNATURE 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 DATE VOID DATE

STD, METER HIGH 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

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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 87M02S MAGNAFLUX 88B019 MAGNAFLUX SKL-HF/S SKC-NF/2C-7B SKD-NF/ZB-9B SPOTCHECK PENETRANT SPOTCHECK CLEANER 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. Il May 1983)'Paragraphs 12,5.1.1 and 12 ~ 5o 1+1.1.

(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.

XAGNhPLUX amoott

anager, ua ty ssurance NOTES:

1.of 2 ~

4.

R 80-P/(

Our batch number appears on the bottom of all aerosol cans and on the label all bulk containers.

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.

The above certification gives the results obtained at the time of manufacture.

Age and use may alter the properties of any material.

PAGE OF '7 MAGNAFLUx.Ab~is~onot tthnos Toot Wnts tnc

..'F m No ~ 1/69 R 8/89 306lndustriat Stteet I PO Box 366 i, QeWilt lttwafiPLA9,.$. To>onbnno qtaMaA>aw,l...ie;11ARCA07t3...

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To consort "percent" flgerea to "porta.per nCLLLon"'!,"':.c$

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$ 5 ~ OT. vay LSTC'sn4 October llTS LncludlngQtndssncs.

L (1 4'l4):sa4 ='~,'

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$000;,grr.

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Date:

October 25,.1989 Purchase Order/Contract No.

C90663 90169 We hereby certify that the Batch Nio 89K039 Spotcheck Penetrant, Type SKL-HF/S 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:

(a)

Flash Point (PMCT), 4.5.3 (b)

Viscas1ty~(

5 n'4 ns NominaB, 4.5.4 t

(c)

Developer Fluorescence, 4.5.14 (d)

Water Content, 4.5.2I

(e)

Penetrant Removability, 4.5.1f ( ~

Standard)

(f)

Wa ter Tolerance, 4.5.12 (g)

Fluorescent Brightness of Penetrants, 4.5.7 (

Standard)

(h)

Surface Netting, 4.5.6 (i)

Thermal Stability, 4.5.9 (J)

Redispersibili ty, 4.5.13 (k)

Valve Leakage, 4e5.20 (I)

Net Content, 4.5.19 209 OF 3 00 cs 4 100oF NA NA Passes NA NA Passes NA NA NA 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.

NAGNAFLUX

~I.J. Plamoottil -.'tanager, Quality Assurance

."-c."m No. 15. 9B

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tho above ostarl ~ Li I, Vesta the restulreaentt Ot Snd haa bren teated ter Su)Cur ¹n4 halOgena aCCOF4lng tOC

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88 08 APPENDIX H EXAMINATIONPROCBDURES PROCEDURE NUMBER REVISION FIELD NUMBER CHANGE TITLE NDE 3.3 NDE 5.4 NDE 5 ~ 19 2

N/A N/A 0 FCA N/A LIQUID PENETRANT EXAMINATION SOLVENT REMOVABLE VISIBLE DYE TECHNIQUE ULTRASONIC EXAMINATIONOF AUSTENITIC PIPING WELDS ULTRASONIC EXAMINATIONOF SOCKET WELDS IN PRESSURIZER AUXILIARYSPRAY LINE (PTN3&4) 24

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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 NUMBER DESCRIPTION DRAWING NO.

UT-53 UT-54

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PZNAL REPORT OP ZNSERVZCE INSPECTION NONDESTRUCT1VE EXAMXNATXONS OF

'NISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFPECTS REFERENCE NRC BULLETIN NOe

'88 08 APPENDIX Z LIQUID PENETRANT DOCUMENTATION LOG DATA SHEET NUMBER

3. 3-201

3. 3-202 3.3-230 3 ~ 3 233 IDENTIFICATION NUMBER 2"-CH-1310-1 2"-CH-1310-2 3"-CH-1301-42.

3"-CH-1301-43 DESCRIPTION REDUCING TEE PIPE PIPE - VALVE 3-313 PIPE - ELBOW ELBOW - PIPE 26

LIQUIDPENETFNNT EXAMINATIONDATASHEET Procedure No.

N Revision z

Data Sheet No.

.2-Ro I Page i

of~

Plant Name/Unit:

Il Identification of Item Examined:

Z-RC-I Examiner's Name: ~~

o l Date:

iso.

00 SNT Level CLEANER PENETRANT REMOVER DEVELOPER Brand:

X Brand:

Brand:

Type:

C-Q Type:

L-Type:

Type:

P-'fg BatchNo. p&&ZS BatchNo.QJ(~Q BatchNo. ~7AAO 5 Batch No.+~~0 Time Applied~>~

Cleaning Removal Completed ~l+Cr DwellTimetPf g

Completed ~Dq 5

Time Read 0'i '5 Z-AdcMonai Information

. SketchAttached~<

Temperaturehl+I~TThermometer S/N N

..... Camera Photo Attached

+0 Other Ind.

No.

L Location W

Up or Round or Location Downstream Linear Dia. or Lenght Accept/

Reject Sketch:

NOTE.:

BATE.

TP TH POLLoW lM Q PER.FOKV E.D Z,",- Rc-la<o-Z.',Pt, ta IO-z- $?c.- l.5t o-Z."- RC.- ll(O-Reviewed by E

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Procedure No.

Revision Plant Name/Unit:

E, 3.

LlQUIDPENETRANT EXAMINATIONDATASHEET Data Sheet No Page Date:

3,3-Zo Z.

I,f l

QZ;I( -Rc CIS-5 tdentification of Item Examined:

Examiner's Name: ~

Iso:

SNT Level OQ

-A i

CLEANERlA~

Type:.

Batch No. '22bhQZ9 Title REMOVER

'EVELOPER Brand:

Brand:

~X ype:

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ype:

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-58 BatchNo. 9MM9 BatchNo. 3~~5 Batch No. 99> @<iR Time Applied~C Cleaning Removal Completed ~COO DwellTime

>7 C 7 Completed O'AD%5 Time Read A

al Information Sketch Attached Temoeratortarthtttrr!SLIT Thermometer S/M NO N

CameraPhotoAttached~+

Other Ind.

No.

L Location W

Up or Round or Location Downstream Linear Dia. or Lenght Accept/

Reject Sketch:

H()~E. '. QU<

TO 7 HE-C LWE. PR.OX)M ll //'l= T'E FOLLOWINth W EL+5 ALL EXAMI NATIONJ PATE R. i=O RME O 6 I IVtu L rorNEOIAS LY Z-,", Rl" {3iO-t 4-,",- RC - (BC'- 4 z,",Rc.- l5lo-Z.

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'70 Form 3325 (Hon45ocked) Rev. 10l88

Procedure No.

UQUID PENETRANT EXAMINATIONDATASHEET Data Sheet No.

~ 23o Revision Plant Name/Unit:

Wl Identification of Item Examined: >-

Examiner's Name:

Page~oi~

Date:

Iso; 6 0 8 SNT Level REMOVER DEVELOPER Brand:

Brand:

Type:

- 8Type:

Batch No.~

Batch No. ~222 Type: >C -

Type:

Batch No. ~4~

Batch No. ~~~9 Time Applied~i'leaning Removal Campleted J~S~~

DwettTime

>VO t

Campteted ~t "I ~

Time Read~hg SketchAttached~>

Temperatvre~

Thermometer S/N Camera Photo Attached No Other Ind.

No.

L Location W

Up or Round or Location Downstream LInear Diaor Lenght Accept/

Reject Sketch:

PDjG.'~t~1 dC~fiu

~7 TO<. Of-Veld, ~64'<t~~~'~"

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LIQUIDPENETRANT EIOLMINATIONDATASHEET Data Sheet No.

~ 3 2 3 3 CIS-5 Revision Plant Name/Unit:

ll Identification of Item Examined:

n Examiner's Name:

CLEANER REMOVER Page

(

of Date:

> -> 3-Iso:

oc SNT Level DEVELOPER Brand:

Type:

c.-

Brand:

Type:

Batch No. +~~

Batch No. ~~~

Brand:

Type:

c-7 Batch No. ~17@~07~

Brand:

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z i/f Batch No.~~~

Cleaning Removal Completed ~<~

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Time Applied t rrO Time Read~<> 0 Additional Information Sketch Attached ~O Temperature ~~ Thermometer S/N Camera Photo Attached ~0 Other Ind.

No.

L Location W

Up or Round or Location Downstream Unear Dia. or Lenght Accept/

Reject Sketch:

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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 NUMBER 5'-43 5'-44 IDENTIFICATION NUMBER 3 n -CH-1 3 01-4 3 3 n -CH-13 01-4 2 DESCRIPTION ELBOW PIPE 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 DATA SHEET NUMBER 5 '9-1 5.19-2 5.19-3 2"-RC-1310-1 2"-RC-1310-2 2n RC 1310 2

REDUCING TEE PIPE PIPE VALVE 3-313 PIPE - VALVE 3-313 APPENDIX K ULTRASONIC EXAMINATIONDOCUMENTATION LOG IDENTIFICATION DESCRIPTION NUMBER 28

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e CALIBRATIONDATASHEET CIS-1 4

5 6

7 8

9 10 ITEM TEMP.

COMMENTS/REASON FOR INCOMPLETED SCANIS)

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IL E omorqre:~~

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Serial No:

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70

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Size & Shape:

'~+

~i~

60 o

50 F eq.: ~>+

Mode: SEREE ~

Freq ence:

40 F rz'o Filter:

A/~

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30 OEC/Gate:

A Cabie BhC -%7 D Art Zrg Gain:

C P

..,-~50 Scan Sent:

AK I8 CX 0

1 2

Edq r lr h:

R{A 1{oh md{eh

{farl RECOROAELE INDICATIONS EXAMINATIONAREA/WELD YES NO GEOM.

Oats Sheet P

/

sge of Procedure No.

h/bC ~ 0 Rev/Chng. No.

or AMPLITUDE High Low AMPLITUDE High Low rl Each Major CRT Oiv. en

~ 3 CRT Calibrated in:

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Scan Area:

0

WRV, 0

Mt'I

Weld,

~II

\\o W ld INST. VERT. LINEARITY 3 -ch'-Zyo/- 'fS 5

SETN/zEN Cz5 ~o 7.so" 5M/F'xTEb v8 /FW V PAv'4 bus <o rnrivaE Aoiu.

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DATE z-i9'-O'Q zP~IFQ CAL. CHECKS TIME Initial Cal.

I Intermed.

Intermed.

F{n.l C.li

/'4'D

Zone/Iso 0 5 OO Plant/Unit

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5 6

7 8

9 10 ITEM TEMP.

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RECORDABLE INDICATIONS COMMENTS/REASON FOR EXAMINATIONAREA/WELD YES NO GEOM.

INCOMPLETEDSCANISl Data Sheet 5 I Page 4ol Procedure No.

5 Rev/Chng. No.

Cal. Block Temp.

Thermometer S/N r/

Each Major CRT Oiv. ~

CRT Calibrated in:

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DATE LEVEL DATE

~~~y ~z&JZg CAL.CHECKS TIME Initial Cal.

I<<

Intermed.

lntermed.

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INDICATION REPORT SHEET C IS-2 Calibraticn Data Sheet Number:

In Zocaticm:

Ou=f5X E.

RAbr.u5 Examiner TC-1A-e Item Identificaticn: ii 3-c -/ ol-3 Ocapmnt %idmess:

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Ol WKL Scan Area:

wel I to weld E

mi r: C-1A-Level N7

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51

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Range:

CALIBRATIONDATASHEET SEARCH UNIT Exam angle:~~

Mode:39g0 Rxx Exx (N(): I-C. ITE ap Brand SE S/N:

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Rep. Rate J~cQ OEC/Gate:

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Gain:

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EXAMINATIONAREA/WELD Size 66 Shape:

Style/Type:

Frequency:

Measured angl ~:

/

Cable:

C pl tbrand: 0 ~s4 Couplsnt batch:

RECORDABLE INDICATIONS YES NO GEOlL 60 40 20 10 COMMENTS/REASON FOR INCOMPLETED SCANlS)

ITEM TEMP.

0 1

2 3

4 6

6 7

8 9

10 to Weld, to Wel INST. VERT. LINEARITY AMPLITUDE High Low AMPLITUDE High Low Thermometer S/N o

Each Major CRT Div. AE CRT Calibrated in:

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/Depth Cal. Direction: Axial,Circ.~ot Scan Ares:

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~3 5 ~cAL gd E x 5 CAL.CHECKS TIME 40 20 x6

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EXAMINERS D.

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CALIBRATIONDATASHEET CIS-1 Data Sheet INSTRUMENTSETTINGS Mlg./Model:

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SL-zia Serial No:

2J 2

Dajag:~ZRange:~

M'tlCsl:

Z SL Daanjgnjj:~+rjj+tj ajanra:

aDFa Freq.:

2 Z5 Mode ~gOg L6 Filtert ~+

Rep. Rate: ~//H0 OEC/Gate:

A REEVE Enn:~N Gain:

Z.O 18 Scan Sans:

X A 6dB switch:

/I

.. he 14dB switch:

EXAMINATIONAREA/WELD 3 -I" -/30/-'I/2 SEARCH UNIT Exam angle:~

Mode:

gp

5@A 80 Size 6L Shape 50 FrtKIUencpt a ~

4p Cable.

AC

/178

~f

.-<<j~a 60 30 RECORDABLE INDICATIONS YES NO GEOSjL COMMENTS/REASON FOR INCOMPLETEDSCANlSl BAIIhzaijh'I 15 vo /. z5 s<AhI z,xhtsx.veD vo hh'a. v Pew btLe 7o Xhthhth WCh OI=<h/E KC8OHh AL50 BALLL ex SA'/5.

NCn E':

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'X ITEM TEMP.

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3 4

5 6

7 8

9 10 Procedure No.

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So 5o 25 2 ~D 20

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AMPL.CONTROL LINEARITY Rev/Chng. No.

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0 WRV, 0 Mt'I

~

J to Weld II to Weld INST. VERT. LINEARITY AMPLITUDE AMPLITUDE c E'LT-53 2A/Lf'ECL Initial h,dB Result Or 7-4/4 kT-53 S fN SAAE PhHXmas'wcAhth~j hshh 8S

%PE'C 2'E5.

60 60 40 20

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DATE LEVEL DATE CAL. CHECKS TIME Initial Cal.

O 8+

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INDICATION REPORT SHEET C IS-2 Calibration Data Sheet Raher++~~

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Additianal RaaMcs:

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Further Evaluatica Required Yes

sv CHKD.BY Q

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oi.

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Mode: ~~<El I0 Procedure No.

INSTRUMENTSETTIN Mfg./Model:

I' Rev/Chng. No.

~

.. ul-pp Fixturing lifsny):

Serial No 80 70 60 D...:~>5 R

M'tlCsl:

DpllpllÃM+~plpcc~

F pq.:lkpal8p>>L Mpdp~

Filterl~

Rep.

Rate'rand SI S/N:

n Size SI Shape:

Style/Type:

Frequency:

Measured angle:

C'bfe:

DEC/Gate:

Video:~i BOOV Switch:~iCC Gain:

u+2J C

6dB switch:Cled 14dB switchtCK4~

EXAMINATIONAREA/WELD Couplant brand:

Ya Couplant batch:

RECORDABLE INDICATIONS YES NO GEOM.

/I-Rc-(

Iz Each Major CRT Oiv.

CRT Calibrated in:

Sound Path Depth Csl. Direction: ~Axial Circ., Both Scan Ares:

0 WRV, 0 Mt'I

~

to Weld, II to Weld INST. VERT. LINEARITY 50 30 20 10 0'

2 3

4 5

6 7

8 9

10=/."

AMPLITUDE AMPLITUDE High High Low Low ITEM TEMP.

COMMENTS/REASON FOR INCOMPLETEDSCAN(Sl

~-n 6 ~C.

+u 33 M

/0 9

10

, ~o 4

70

, ~d AMPL.CONTROL LINEARITY Initial 80 80 40 20 Q dB

-12

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'EVEL DATE LEVEL DATE W7

.0 CALCHECKS TIME i MRC t. D'7 rp Intermed.

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CALIBRATIONDATASHEET CIS-1 D.t.Sh 5 I'I-I Page of P.ocedure No.

Rev/Chng. No. ~e"I Cal. Block Temp.

A IId'hermometer S/N I/

Each Msior CRT Div. 44

~ /~

CRT Calibrated in:

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0 WRV, 0 Mt'I to Wel II to Weld INST. VERT. LINEARITY 4

5 6

7 8

9 10 =/.~"

0 1

2

.g-J.l'.yd.8'si~

COMMENTS/REASON FOR INCOMPLETEDSCANIS)

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Mode%~1 4/

gp

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Re/>> E.tc. i>>

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30 OEC/Gstet 4 8u/'-wrO Vdoe~

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+

Co Faoel aemd:

tt 10 Gain:

ph Scen San,.

2o tl')

2 I-'~ok)>

44E I IaavM/g aadd oellaa.~ag AECDADAELE INDICATIONS EXAMINATIONAREA/WELD YES NO GEOM.

AMPLCONTROL LINEARITY EXAMINERS REVIEWERS LEVEL DATE

/

LEVEL~

DATE

~ /7 Jcr < ///'/ /Q//

CAL. CHECKS TIME l MalCM ~0 Intermed.

Intermed.

Fl IC I

/ w//

Initial 80 80 40 20 b, dB

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INDICATION REPORT SHEET Calibration Data Sheet Number:

Item Identificaticm: 2" Q Q I31g (

Zo Zacatian: TQ g Wo Zacatice: Q5 T p

)J Ex i

TC-A- vel E

i

C-1A-Level 3

of 3 n-Ocaponent 'Ihickness: t~i

=,

ec Dianater

~

Scan Area:

to weld I~ 90 Angle of DAC 20 goal OI/

50 20 os S.U.

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Bxrther Evaluation Bapured Yes

Zone/iso Plant/Unit Comp/System F

INSTRUMENTSETTINGS MfgJModel:

CALIBRATIONDATASHEET c//unrig 8r SEARCH UNIT 0

E arrl mal:~ Mode:~P gp CIS-1 Oats Sheet SE l t 2.

Rev/Chng. No Pape~ I~

. ~

.. ~C

~A ap TI$

~t Serial No:

1 tr Rerav:~'amp:~

M'tlCsl:

Damping:~LE Reject:~'r~.t

~8Mw/LM~: Q~/.

Firmrr~Trt'ep. Rare~REM OEC/Gatet Video:

~, A/

600V Switch:UgC{

Gsint Scan Sent:

VFA 6dB twitch:

14dB t itch:@LE~~

EXAMINATIONAREA/WELD

"-8.c-]

Fixturing lifsny):

Brand &S/N Size &Shape:

Style/Type:

Frequency:

O Measured angler AfC-NTQ Coup!ant brand:

RECORDABLE INDICATIONS YES NO GEOM.

f~&

o"-

'0 70 60 50 40 30 20 10 0

1 2

4 5

6

~ $L der/Etym Og 5$tgfprR~

COMMENTS/REASON FOR INCOMPLETEDSCANISl Fr g

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8 9

ITEM TEMP 6'r-Cal. Block No.

//l Thermometer S/N 0

10= i.2 AMPLITUDE AMPLITUDE Highle S ~~

Low High Low

~<6 M>

88~

AMPL.CONTROL LINEARITY ll EaeaM IorCRTOiv.

CRT Cshbrated m Sound Pat Depth Cal. Direction:

xia Circ., Both Scan Area:

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to Weld II to Weld INST. VERT. LINEARITY I

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Initial 80 80

!5 d8

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t x1 aTe te eS'r EXAMINERS REVIEWERS LEVEL~ RATE LEVEL DATE

<

CAL. CHECKS TIME Itr IC I. ~R Intermed. ~~~ I at ~ mee. ~P> F.I C I. ~l< V 40 20 tE ~ET t12 CIS-2 Calibration Data Sheet Number: INDICATION REPORT SHEET Io tucatice: D g >.l9-2. of Ex i TC-A- velI Item Idectificatice: 2"-g (3)II-Q 'N Iocaticm: )( p g () (valent Thic)mess: =. " J e 2" Diameter Scan Area: I to weld Exam'0 r: C- -Level C-Angle 20 /0 CU /E 4> 50 20 .4o'.U. IOC. @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 BY CHKD. BY o*rg ~ DATE ~ ~O >, I 5'- Z SRE-43 Ot PROJ ot3 I ( I I I I I I I Ig I I I I ~ i I ~ i I I: 4 ) I I ) I I ~ 4, I I ~ ~ I ~ I I 4 I I I I a I I I I I ~ I I g I I I ) I I i I I I I ~ 4 II ~ - 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 h 1 ~ ? ,1 Zone/iso -A Plant/Unit 1 Comp/System v'a INSTRUMENTSETTINGS Mfg./Model: r uf drh Serial No: Delay:~'ange: M'tlCal: Damping:MMRelact:~ Freq.:QSsQtRa J Modrx ~~d< i~ Filters~'ep. Rste~d>el DEC/Gate: Video:3W 600V Switch:MW Gain: dj CALIBRATIONOATASHEET -P eSurrs er Fixturing lifsny) t Brand Si S/N: 70 Size SE Shape: 5 Style/Type: Frequency: EE) 0 Measured sng4t Cable: I -Ahr Couplsnt brand: Couplant batch: 60 50 40 30 20 10 SEARCH UNIT CB Exam angle: ?'I-) Mode:~ g0 80 CIS-1 Data Sheet Eme~or~ Procedure No. ~ / Rev/Chng. No. . vcr.vv O~ Cal. Block Temp. /~* II Each Maior CRT Die. CRT Calibrated in: Sound Path/Depth Cal. Direction:(A~xial irc., Both Scan Ares: 0

WRV, 0

Mt'I ~ ~ to Weld ll to Weld INST. VERT. LINEARITY V e Scan Sans: 3 Edh irch:~lech awircmMi EXAMINATIONAREA/WELD RECORDABLE INDICATIONS YES NO GEOMe 7 0 1 2 3 4 5 6 7 8 9 10 ITEM TEMP. COMMENTS/REASON FOR INCOMPLETEDSCAN(S) ~~Et I ff fO 3 rpm 055rJ~ a Cc. High ldO 3 ~~ 4 7() 40 5 Low High Low 6~ '~5 /I'o 1 8 ~~ 3X N /d 9 AMPL.CONTROL LINEARITY AMPLITUDE AMPLITUDE 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~. 31lis/Ol!54L10 SENT-SSAO-71'll Itev. 0 4. CONCLUSIONS The systems review to determine unisolable sections of piping (item (a) of 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. e 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 I FZOhl ~ T I TOP Inspect only shaded portion of line. w 1d SECTION BM SECTION A 0 '. qA gl ~]W 10 ~~g F PESSURIZER A 0', b<g~~ ~4'o FIGURE A TEMPERATURE ONITORING LOCATION (As close as pcssible to valve outlet) 181 I 1 9e >o 9 ~ p 9 r+ 9p 99 99(+rp 99~lr~ J' >o 99' )g. %g Ref: Isometric Drawing 5613-P-661-S Sheet 2 of 4 Base 8 tal TURKEY POLIT UNIT 4 AUXILIARYSPRAY LINE SE&PT-SSAD-7814 Rev. 0 Inspect on]y shaded portion of tee. sccrioH 8-S sEcTiON A-A gQ h h + yl gab gr ,r4 J1 ~OO ~OO I1 +qO aO~ gC I1~1 ~gO Pl~i B Temperature Monitoring Locati"n (As close as possible to va-'v<<utlet) Ref: Isometric Drav ns 5614-P-782-S Rev. 0, Sheet 'f 3 TURKEY POINT UNIT 3 CHARGING PUMP TO C HOT LEG SE&PT-SSAD-7814 Rev. 0 Temperature Monitoring Location (As close as possible to elbow weld) 20 pV g+ ~pl bb gO ey b yO J l~ 0 y o +0g 0~~ >o~ 8 80~ CU AJ %00~ 00 +S J~~ FIGURE C if@8g ~J Ref: Isometric Drawing 5613-P-66l-S 'Rev. 0, Sheet 2 of 4 TURKEY POINT UNIT 4 CHARGING PUMP TO C HOT LEG SEkPT-SSAD-7814 Rev. 0 SHORT RADIUS ELBQV Iran HQT LEG LOOP C 34'.D. 20'H g+~ ~w ) 2S'H ~g ~n N Iu ~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 'fr operated globe isolation valve (3-IA58RGP). The differential 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 liftcheck 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) ~ (o~n g) lo.l5 Qy Sa'3 ~ $ o}Q ~ ~ S'o.p XSq( o 4 st'0,e C,a'- l$4g 77j X cA W C a O IVl Vl 00 .A A "4k,. w ~ I 4 ILAL 'p (u~n. 4) Li&K Pl@.vs, 2 7f.o I iud e.1 NO ~f.: <<<4 ~~a> >-CL a~y]'%0 C.o Co~ Owe'Q . s:'Qa I A.51 g ~ jv~. Chp. ]r t1 ~l 1 E'l.I~ lg.yg 0.%R'4:S 4 1c'g 4 4Q. ~ Cll A tO O I IP V. 3.4 I I-ov 523 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 s.s 'LCL2'g~ 5 C 27.1L ~-%5 I ~l I <r -1 . ~ (.ol Jot iy~ o.la.'F6e4.~. Zt. iS.% is:s' CAp ~ C.wt Q-IN'A ate'olg % CA l04 0' I ,pl 'c"., s Elan-CLLO-731i ltev, o ATTACHMENT 2 BULLETIN 88"08 EVALUATION INSPECTION LOCATIONS

1. 0 METHOOOLOGY Attachment 1 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.

Mithin 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 [ - (UP/mCp) x ]

c 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 ( 0 ~ - d 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 1I.O 0.8 0 t C3 I 0 0.4 I 0.2 FICURE 2-1 CONDUGTlON FRED CONVECTKN FOR HPS 3" AND QNLLER 311$ o/042248 lO 0.0 0 DISTANCE'FROM HOT LEG, (FT) EFFECT OF MOLECULAR CONDUCTION AND FREE CONVECTION ON AXIAL TEMPERATURE DISTRIBUTION SE&PT-SSA:-1814 Rev. 0 ATTACSIENT 3 INSPECTION GUIOELINES 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 e one-half vee exam for all of the above welds. Performing an additional 60 degree refracted shear wave examination using 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. > SolOI1%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

tgl lg

/ P $ g 5' g @gal jap gQ Q tt ), VO, l 'W I'h g', gRQA UNITED STATES NUCLEAR RFGULATORY COMMISSION OFFICE OF NUCLFAR REACTOR REGULATION WASHINGTON, O.C. ZC555 June 22, 1988 OHB No.: 31SD-QDll NRCB 88-08 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 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 t 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-tfvcly cold water lcakfng through a closed globe valve at a pressure sufffcfcnt 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 / Discussion: NRCB 88-08 June 22, 1988 Page 2 of 4 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 2. 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. 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 3. 1'PCS 88-n8 "une 22, 1988 Page 3 os 4 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 faflure 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: 10 ~ 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 of Mana ement Budget under clearance number 3150-0011. o anagement and If you.have any ouest1ons regarding thfs matter, please contact one of the technical contacts listed below or the Regional Administrator. f h 'NRC regional office. n s ra or.o the appropriate ..'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:

e 1. figure 1 - Farley 2 Temperature Oata 2. Ffgure 2 - Farley 2 ECCS 3. l.1st of Recently Issued NRC Bul?et$ ns h 8 t t %pe tp'l =p, If@, 'Fpl I c y ~ >> ~ >> J' WllH INTHOLIT LEANAGE LEAKAGE TOP Gf FQ% 448f 4%f IOflONOftltf RNf 4$% FAREO WKLY ICS COLO LE4 ~ IFARLKY2 TEMPERATURE DATA ~ y 4 ) g I l" '," + E qt', l 4 ~ I 'p, 8','.% 8 "/'k< ) $ $ pl 7f'6+~ W f% +Mt'ltp)tCIQ KCCS YO hCS COLO LKOS QOhNALCHAholgo 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

ML17348A320

Contents

Text

1.0 INTRODUCTION

SUMMARY

7.1 DESCRIPTION

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

7.1 DESCRIPTION

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ML17348A320

Text

1.0 INTRODUCTION

SUMMARY

7.1 DESCRIPTION

SUMMARY

SUMMARY

1.0 INTRODUCTION

SUMMARY

7.1 DESCRIPTION

SUMMARY

SUMMARY

Navigation menu

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