ML17345A663

Final Rept of Inservice Insp NDE of Unisolable Piping Sys & Components for Potential Thermal Stress Effects Ref NRC Bulletin 88-008

ML17345A663
Person / Time
Site:	Turkey Point
Issue date:	03/21/1989
From:	Anderson E FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17345A662	List: L-89-176, Responds to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. NDE of Unit 4 Identified No Crack Indications.Nde of Unit 3 Will Be Completed During Cycle 12 Refueling,Currently Scheduled to Begin in Nov 1989 ML17345A663
References
IEB-88-008, IEB-88-8, MCI-PTN-004-88, MCI-PTN-004-88-08-R0, MCI-PTN-4-88, MCI-PTN-4-88-8-R, NUDOCS 8905110029
Download: ML17345A663 (43)

Text

i ATTACHMENT 1 NUCLEAR ENERGY SERVICES MATERIALS, CODES and INSPECTIONS SECTION 700 Universe Blvd.

Juno Beach, Florida FINAL REPORT OF INSERVICE INSPECTION NONDESTRUCTZVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~

88 08 PREPARED BY:

FLORIDA POWER AND LIGHT COMPANY FOR TURKEY POINT-NUCLEAR POWER PLANT UNIT NO ~

4 P+0 ~

BOX 3088 FLORIDA CITY'LORIDA 33034 COMMERCIAL SERVICE DATE! PTN-4 7

SEPTEMBER 1973 NRC DOCKET NUMBER:

DOCUMENT NUMBER:

50-251 MCI-PTN-004-88-08 REV.

0 PREPARED BY'I ENGINEER C&P

~aa REVIEWED BY:

P VI 0 PRO CODES OUP DATE'

~ ~7 APPROVEDBY'ATE:

A ER MATERIALS, CODES

& INSPECTIONS SECTION C~905ii0029 890504 pap" ADOCK C>

OOC>2 0

9 PDC

FINAL REPORT OF ZNSERVZCE INSP CTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 TABLE OF CONTENTS TITLE PAGE/COVER SHEET TABLE OF CONTENTS RECORD OF REVISION ABSTRACT ABBREVIATIONS

1.0 INTRODUCTION

1.1 PROGRAM APPLICABILITY 1.2 INSPECTION INTERVAL 1.3 INSPECTION PERIODS 1 '

APPLICABLE DOCUMENTS 1.5 APPLICABLE CODE EDITIONS AND ADDENDA 2.0 ENGINEERING RECOMMENDATIONS 2.1 CHARGING PUMP TO PRESSURIZER AUXILIARYSPRAY LINE 2.2 CHARGING PUMP TO "C" HOT LEG 3.0 ABSTRACT OF EXAMINATIONS PERFORMED 3.1 APPLICABLE AREAS 3 ~ 1 ~ 1 AUXILIARYSPRAY LINE 3.1.2 CHARGING LINE

~

~

FINAL REPORT OF INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PZPXNG SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 TABLE OF CONTENTS 3.2 LIQUID PENETRANT EXAMINATIONS 3.3 ULTRASON1'C EXAMINATIONS 4.0 ABSTRACT OF CONDITIONS NOTED 4.1 AUXILIARYSPRAY LINE 4.1.1 2"-RC-1410-33 4.1.2 2"-RC-1410-34 4. 2 CHARGXNG LINE 4

2 1

3it CH 1401 32 4.2.2 ELBOW BASE METAL 4

2 3

3't-CH-1401-33 4'.4 PXPE BASE METAL 4.2.5 3"-CH-1401-34 4.2.6 ELBOW BASE METAL 4.2.7 3"-CH-1401-35 4.2.8 PIPE BASE METAL 4.2.9 3it CH 1401 36 4 '.10 ELBOW BASE METAL 4

2 11 3"-CH-1401-37 5

~ 0 CORRECTIVE ACTIONS TAKEN AND/OR RECOMMENDED

FINAL REPORT OF INSERVZCE ZNSPECTZON NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 TABLE OF CONTENTS 6.0 EVALUATION CRITERIA F 1 CLASS 1

6.1.1 ACCEPTANCE STANDARDS FOR CLASS 1

7.0 INSERVICE INSPECTION

SUMMARY

TABLES

7.1 DESCRIPTION

OF TABLES 7.1.1

SUMMARY

PLAN TABLES EXPLANATIONS 8.0 RECORDS 8.1 GENERAL 8.2 INSERVICE INSPECTION

SUMMARY

REPORTS APPENDICES A

REFERENCE DRAWINGS B

PERSONNEL CERTIFICAT10NS C

ULTRASONIC EQUIPMENT D

ULTRASONIC TRANSDUCERS E

ULTRASONIC COUPLANT F

THERMOMETERS G

LIQUID PENETRANT MATERIALS H

EXAMINATION PROCEDURES I

ULTRASONIC CALIBRATION BLOCKS J

LIQUID PENETRANT DOCUMENTATION DATA PACKAGES K

ULTRASONIC DOCUMENTATION DATA PACKAGES L

ENGINEERING RECOMMENDATIONS DOCUMENT SEGPT-SSAD-7814 M

NRC BULLETIN 88-08 THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS

FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS 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

FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE 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 FP&L ISI JNS MCI NDE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE CODES AND PROGRAMS GROUP CHARGING FLORIDA POWER AND LIGHT COMPANY INSERVICE INSPECTION JUNO NUCLEAR ENERGY SERVICES MATERIALS, CODES AND INSPECTIONS SECTION NONDESTRUCTIVE EXAMINATION NRC NUCLEAR REGULATORY COMMISSION PTN-4 RCS RC TURKEY POINT PLANT UNIT NO.

4 MAIN REACTOR COOLANT SYSTEM REACTOR COOLANT

FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE 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 1988 refueling outage which began on 17 September 1988.

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. 4.

NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08

1.0 INTRODUCTION

1.1 PROGRAM APPLICABILITY This Report details the Florida Power

& Light Company's results of Inservice Inspection, Nondestructive examinations performed at the Turkey Point Nuclear Power Plant, Unit No. 4.

1.1.1 The operating License for Turkey Point Unit no.

4 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 April 15, 1984 and ends on April 14, 1994.

1.3 INSPECTION PERIODS The Inspection Interval is divided into three successive inspection periods as defined by Program "B".

Period START END April 15, 1984 April 15, 1987 April 15, 1987 April 15, 1991 3

April 15, 1991 April 14, 1994 1.4 APPLICABLE DOCUMENTS II The Nondestructive examination Program performed during this activity was developed after giving due consideration to the following documents:

ASME BOILER AND PRESSURE VESSEL CODE p SECTION XIg 1 98 0 EDITION THROUGH THE WINTER 1981 ADDENDA, "RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS"

NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 U.

S.

NUCLEAR REGULATORY BULLETIN 88-08 TITLED "THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMSn DATED.

JUNE 22~

1988~

SUPPLEMENT 1

DATED JUNE 24~

1988 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 78 1 4 ~

DATED AUGUST 1988

1. 5 APPLICABLE CODE EDITIONS AND ADDENDA As required by Title 10 of the Code of Federal Regulations.

paragraph 55a (g)

(4) Inservice Inspections requirements applicable to nondestructive examination at Turkey Point Unit 4 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.

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 include portions of the following lines:

2.1 CHARGING PUMP TO PRESSURIZER AUXILIARYSPRAY LINE 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 004-A29, and also, the weld at the outlet of valve 4-313.

2 2

CHARGING PUMP TO ttC" HOT LEG All welds from the third to fourth elbow down stream of check valve 4-312B (4 weld locations) and base metal of the fourth elbow downstream of check valve 4-312B as identified on isometric drawing 004-A39.

FZNAL REPORT OF ZNSERVZCE 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 3 '

APPLICABLE AREAS Based on the recommendations identified above the following items were scheduled for nondestructive examination.

3.1.1 AUXILIARYSPRAY LINE DRAWING 004-A29 ZONE IDENTIFICATION DESCRIPTION EXAM METHOD 035 2"-RC-1410-33 VLV 4-313 PIPE UT

& PT 035 2"-RC-1410-34 PIPE RED.

TEE UT

& PT 3.1.2 CHARGING LINE LOOP C DRAWING 004-A39 ZONE IDENTIFICATION DESCRIPTION EXAM METHOD 045 3"-CH-1401-32 V

ELBOW 3n-CH-1401-33 PIPE 3"-CH-1401-34 ELBOW 3't-CH-1401-35 PIPE 3"-CH-1401-36 ELBOW 3"-CH-1401-37 PIPE ELBOW BASE METAL ELBOW PIPE BASE METAL PIPE ELBOW BASE METAL ELBOW PIPE BASE METAL PIPE ELBOW BASE METAL ELBOW PIPE UT

& PT UT

& PT UT

& PT UT

& PT UT

& PT UT

& PT UT

& PT UT

& PT UT

& PT UT

& PT UT

& PT 10

FINAL REPORT OF ZNSERVICE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 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 and a

new calibration block had to be fabricated for the examination of socket weld areas.

The procedure and calibration block were qualified and demonstrated to the satisfaction of the Authorized Nuclear Inservice Inspector on January 26, 1989.

NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 4.0 ABSTRACT OF CONDITIONS NOTED Described below by component is a summary of conditions noted during the Unit No.

4 examination activity:

4.1 AUXILIARYSPRAY LINE 4 ~ 1 ~ 1 ZONE 035 ~

2 RC 14 10 33 f VLV 4 3 13 PIPE A liquid penetrant and ultrasonic examination using a 45 and 70 degree search unit.

ONE (1) indication recorded with a

amplitude recorded to be less than 204 DAC, determined to be probable beam redirection.

4.1.2 ZONE 035( 2"-RC-1410-34, PIPE RED.

TEE:

A liquid penetrant and ultrasonic examination using a

45 and 70 degree search unit.

NO RECORDABLE INDICATIONS NOTED 4.2 CHARGING LINE LOOP C

4.2.1 ZONE 045 f 3

CH 1401 32 g PIPE ELBOW A liquid penetrant and ultrasonic examination 'using a

45 and 60 degree search unit.

NO RECORDABLE INDICATIONS NOTED 4.2.2 ZONE 045, ELBOW BASE METAL:

A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

NO RECORDABLE INDICATIONS NOTED 4.2.3 4 ~ 2 ~ 4 4.2.5 ZONE 045 3it CH 1401 33'LBOW PIPE A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

Two (2)

GEOMETRIC INDICATIONS were noted and determined to be caused by root geometry.

ZONE 045, PIPE BASE METAL:

A liquid penetrant and=-ultrasonic examination using a

45 and 60 degree search unit.

NO RECORDABLE ZONE 045 3n-CH-1401-34, PIPE ELBOW A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

Two (2)

GEOMETRIC INDICATIONS were noted and determined to be caused by root geometry.

12

FINAL REPORT OF INSERVICE INSP TION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 4.2.6 ZONE 045, ELBOW BASE METAL:

A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

NO RECORDABLE INDICATIONS NOTED 4 ~ 2

~ 7 ZONE 045 g

3 CH 1401 35 ~

ELBOW PIPE A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

NO RECORDABLE INDICATIONS NOTED 4.2;8 ZONE 045, PIPE BASE METAL:

A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

NO RECORDABLE INDICATIONS NOTED 4 ~ 2 ~ 9 ZONE 045 g 3

CH 140 1 36 g PIPE ELBOW A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

NO RECORDABLE INDICATIONS NOTED 4.2.10 ZONE 045, ELBOW BASE METAL:

A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

NO RECORDABLE INDICATIONS NOTED 4.2.11 ZONE 045 3n-CH-1401-37, ELBOW PIPE A liquid penetrant and ultrasonic examination using a

45 and 60 degree search unit.

NO RECORDABLE INDICATIONS NOTED 13

FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS

'FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 5.0 CORRECTIVE ACTIONS TAKEN OR RECOMMENDED All indications noted were evaluated in accordance with the requirements of the ASME Boiler and Pressure Vessel

Code,Section XI (were acceptance criteria exists).

There were no indications that exceeded the acceptance criteria of the ASME Code, IWB-3000.

14

FINAL REPORT OF INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTZAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 6.0 EVALUATION CRITERIA During Inservice Inspection, flaw indications are evaluated against the acceptance standards of 'he ASME Code as follows:

6. 1 CLASS 1

6.1.1 Acceptance standards for class 1 are as follows:

EXAMINATION COMPONENTS OR PARTS EXAMINED ACCEPTANCE CATEGORY STANDARD DISSIMILAR AND SIMILAR METAL IWB-3514 WELDS IN PIPING 15

~

~

FINAL REPORT OF INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~

88 08 7.0 INSPECTION

SUMMARY

TABLES

7.1 DESCRIPTION

OF TABLES The TURKEY POINT PLANT UNIT 4 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.

7.1.1

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 16

NDX 'CORPORATION ZSIC ISI Data Management System FLORIDA POWER 4 LIGHT CO ~

TURKEY POINT NUCLEAR PLANT UNIT 4 ZNSERVICE INSPECTION FINAL REPORT TABLES RESULTS FOR OUTAGE 1 (1988)g, SECOND PERIODS SECOND INTERVAL

SUMMARY

NUMBERS 111500 THROUGH 111600 March 20, 1989 REVISION 3

DATE:

03/20/89 REOISION:

3 AUXILIARY SPRAY LIHE TURKEY POINT NUCLEAR PLANT UNIT 4 INSERVICE INSPECTION FINAL REPORT TABLES OUtAGE 1 (1988),

SECOND PERIOD, SECOND INTERVAL CLASS 1

COHPOHEHTS PAGE:

1 ZONE NUHBER: 035 SUHHARY EXAHIHATI OH AREA HUHBER IDENT IFI CATION ASHE SEC. XI CATGY EXAH ITEN NO HETHCO PROCEDURE N I 0

S OHGT T

RSEH A

E I 0 E

REHARKS T

C 0 H R

• ~CALIBRATIOH BLOCK~~

R F

0 NO 004 A

111500 2"-RC-1410-33 VALVE (4-313) -

TO - PIPE 75 I 0 II 8 J e9.21 P'I NDE 3.3 342 C

C UT 45 AX NDE 5.19 1

C UT 70 AX HDE 5.19-1 C

1-28.89 UT COHPLETE

~~UT.44 111600 2".RC.1410-34 PIPE TO - RED.

TEE 75 '0" 8-J 89.21 PT HDE 3.3.341 UT 45 AX HDE 5.19-1 UT 70 AX HDE 5.19 1

C C

1.28.89 UT CCHPLETE

• AQT 441*

rrDx coRpoRATIorr

~

rsrc rsr bdcd rrdh890$ 0!lt sgstclll FLORIDA POWER fi LIGHT CO ~

TURKEY POINT NUCLEAR PLANT UNIT 4 ZNSERVZCE INSPECTION PZNAL REPORT TABLES RESULTS FOR OUTAGE 1 (1988) i SECOND PERIODi SECOND INTERVAL

SUMMARY

NUMBERS 154800 THROUGH 155300 March 20, 1989 REVISION 3

DATE:

03/20/89 REVISION:

3 CHARGE LINE RHX TO COLD LEG OOP C

TURKEY POINT NUCLEAR PLANT UNIT 4 IHSERVICE INSPECTION FIHAL REPORT TABLES OUTAGE 1 (1988),

SECOND PERI(X)l SECOND INTERVAL CLASS 1

COHPONEHTS PAGE:

1 ZONE HUHBER: 045 SUHHARY EXAHINATIOH AREA HUHBER IDEHTIFICATIOH ASHE SEC. Xl CATGY EXAH ITEN NO NETNOO PROCEDURE N I 0

S OH 0T T

RSEH A

E I 0 E

REHARKS T

C G H R

• >>CALIBRATIOHBLOCK*t-REF.

DMG. NO. OOC-A39 154800 3".CH-1401.32 PIPE TO -

ELBOM 23 I 9 II 23'-9" 8-J 89.21 PT NDE 3.3 288 UT 45 AX HDE 5.4-25 UT 45 CIRC NDE 5.4 25 UT 60 AX HDE 5.4-25 C

C C

C C

10-19-88 PT COHPLETE: 10.24 88 UT C(WPLETE t>>UT.CC>>t 15C850 ELBOM (32.33)

ELBOM.BASE HETAL 23'.9" 23 I 9 II 8 J 89.21 PT NDE 3.3.304

'T 45 AX HDE 5.4-25 UT 45 CIRC HDE 5.4 25 UT 60 AX HDE 5.4 25 C

C C

C C

10-24-88 UT COHPLETE 10-19-88 PT COHPLETE t*UT-44*>>

154900 3"-CH.1401-33 ELBOM -

TO - PIPE 23 I 9ll 23 I 9 II 8-J 89.21 PT NDE 3.3.287 UT 45 AX HDE 5.4-25 UT 45 CIRC NDE 5.4.25 UT 60 AX HDE 5.4 25 C

C 10.19.88 PT COHPLETE: 10.24 F 88 UT COHPLETE: 2 IHDS. (1) 45 AX, 30K DAC, HL*3.7CCM, HM*1.27, HP>>1.85,DS:

(2) 60 AXI 35K DAC, HL>>3. 7CCM, HM"-.95, HP>>. 75 ~

DS:

• • MT 44tt 154950 PIPE (33.34)

PIPE BASE HETAL 23'"

23 I 9 II 8 J 89.21 PT HDE 3.3-281 UT 45 AX HDE 5.4-25 UT 45 CIRC HDE 5.4 25 UT 60 AX HDE 5.4.25 C

C C

C C

10 19-M PT COHPLETE: 10.24-88 UT COHPLETE

• >>O'I-44*>>

155000 3>>-CH-1401.34 PIPE TO -

ELBOM 23'-9" 23 I 9 II 8 J 89.21 PT NDE 3.3-286 UT 45 AX NDE 5.4-25 UT 45 CIRC HDE 5.4 25 UT 60 AX HDE 5.4 25 C

C 10.19-88 PT CNPLETE: 10-24.M UT COHPLETE: 2 INDS, (1) 45 AX, 30K DAC, HL>>1.4CMI HM 1.31, HP>>1.9, US:

(2) 60 AX, 20K DAC, HL>>I.CCM, HM*,71, HP=.75, US:

t UT-44>>t 155050 ELBOM (34.35)

BASE HATERIAL 23'-9" 23 I 9 II 8-J 89.21 PT HDE 3o3 290 UT 45 AX NDE 5.4-25 UT C5 CIRC HDE 5.4.25 UT 60 AX HDE 5.4-25 C

C C

C C

10 19.88 PT CNPLETE:

10 24 88 UT COHPLETE t UT-44*>>

DATE:

03/20/89.

REVISION:

3 CHARG LIH RHX TO COLD LE LOOP C

TURKEY POINT NUCLEAR PLANT UNIT 4 INSERVICE IHSPECTION FINAL REPORT TABLES OUTAGE 1 ( 1988) I SECOND PERIOD I SECOND INTERVAL CLASS 1

COHPOHEHTS PAGE:

2 ZONE NUHBER: 045 SUHHARY EXAHI NATION AREA HUHBER IDEHTIFICATION ASHE SEC. Xl CATGY EXAH ITEH NO HETHDO H I S

OH 0 T

RSE A

E I 0 PROCEDURE T

C G H H

E REHARKS R

~~CALIBRATION BLOCKii REF DlJG.

NO. 004-A39 155100 3"-CH-1401.35 ELSOM TO - PIPE 23 I 9ll 23 I 9ll 8-J 89.21 PT HDE 3.3-285 UT C5 AX NDE 5.4 25 UT 45 CIRC NDE 5.4-25 UT 60 AX NDE 5.4 25 C

C C

C C

10-19 88 PT CCHPLETE: 10-24.88 UT COHPLETE 155150 PIPE (35 36)

PIPE BASE HETAL 23 I 9 II 23 I 9ll SJ PT HDE 3.3.291

8921, UT45 AX NDE54 25 UT 45 CIRC NDE 5.4 25 UT 60 AX HDE 5.4-25 C

C C

C C

10.19.88 PT COHPLETE: 10-24-88 UT COHPLETE e UT-44~~

155200 3".CH-1401-36 PIPE.

TO ELBOM 25'5' J

89.21 PT HDE 3.3.284 UT 45 AX HDE 5.4 25 UT 45 CIRC NDE 5.4-25 UT 60 AX HDE 5.4-25 C

C C

C C

10.19.88 PT CCHPLETE: 10-2C-88 UT COHPLETE 155250 ELBOM (36-37)

BASE HATERIAL 25'5' J

89.21 PT NDE 3.3.289 UT 45 AX NDE 5.4-25 UT 45 CIRC NDE 5.4 25 UT 60 AX HDE 5.4 25 C

C C

C C

10 19-88 PT CCHPLETE: 10-24.88 UT COHPLETE t UT-44~~

155300 3"-CH-1C01-37 ELSOM -

TO - PIPE 8-J 89.21 PT NDE 3.3.283 UT 45 AX NDE 5.4-25 UT 45 CIRC NDE 5.4.25 UT 60 AX HDE 5.4.25 C

C C

C C

10.19.88 PT COHPLETE: 10-24-SS UT COHPLETE 11@ 44t*

~

~

FINAL REPORT OP ZNSERVZCE INSPECTZON NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 8 '

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 SUGARY 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.

17

t FINAL REPORT OF ZNSERVZCE ZNSP CTZON NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS

~

REFERENCE NRC BULLETIN NO ~

88 08 APPENDIX A REFERENCE DRAWINGS DRAWING NUMBER REV.

NO.

004-A29 004-A39 TITLE 2" AUXILIARYSPRAY LINE 3" CHARGING LINE 18

4 -RC-1404 4

PRESSURIZER SPRAY CONT. ON OWG. 004-A14 REDUCING TEE 3 -CH-1401

~

3 CHARGING CONT. ON OWG. 004-A39 REO.

'-311 WR-63-2 SR-922 229-0 25 2 -RC-1410 5

SR-933~

SR-932' SR-927

"-'-'-'L~

21 22 779-C 1

10 13

~EL 24'-0 WR-39 19 18 779-8 779-A

~ER-930 12 6

15 BIO SHIELD WALL 16 17 SR-93 920 O NRC BULLETIN 88-08 lHERMAL SlRESSES OVe. 5614-r -782-S 32 31 30 WR-63-1 WR-63-3 O

2 II SR-923-B SR-923-A ll 26 II 27 28 2 -RC-1410 SR-926 REFERENCE DRAWINGS PRESSURE dc TEMPERAlURE STATS MATERIAL SPECS SIZE SCH TYPE CODES dc PROGRAMS GROUP lURKEY POINT UNIT 4 5177-102-SK-P-875 REV. C 5610-lE-4501 SHT.

1 OF I 5610-M-410-214 SHT. 3 OF 3 5610-M-410-202 SHT. 2 OF 2 DESIGN PSIG: 2485 TEMP(F): 650 OPERATING PSIG: 2235 TEMP(F): 550 HYDROSTAllC PSIG: 2335 TEMP(F): 547 UT CAUBRAllON BLOCK: N/A DATE:26 SEPT 1988 REVISION APPROVEO BY:

3 2

160 A376-lP316 SMLS TITLE:

2 AU)4 SPRAY UNE ZONE: 35 DRAWING NUMBER:

004-A29

14 I

I I

15 BIO. SHIELD 16 WALL 17 19 4-VCH-5 20 21 22 23 WR-41 24 25 NRC BULLETIN 88-08 0 THERMAL STRESSES 5614-P-782-S 26 30 28 4-312B Q

FLOW WR-41A 4-VCH-13 PASPMB'AL 31 PIPE Q7 29 -RCS-1408 MAIN REACTOR COOLANT CONT. ON DWG. 004-AB HQIB 3 -RC-2501R-3 5177-102-SK-P-876 LOCATION:

CONTAINMENT C

LOOP HOT LEG E-2389-10-297 E-2389-10-479 SR-944A ltj I

I I

I 3'HARGING CONT. ON DWG. 004-A40 2"-RC-1410 2

AUX. SPRAY CONT. ON DWG. 004-A29 I

7 I

8 I 4-311 8A 3 -CH-1401 6

5 L~ 936 9

SR-934 11 4-310A 12~SW-S43 29, 4-VCH-14 3 -CH-1402 ~

Og 4

Q BASE IIETAL ON ELBOW BASE METAL ON PIPE BASE METAL ON ELBOW REFERENCE DRAWINGS PRESSURE dc lEMPERAlURE STAlS MATERIAL SPECS SIZE SCH TYPE

~pg~

CODES dc PROGRAMS GROUP TURKEY PONT UNIT 4 5177-102-SK-P-876 REV. C 5177-102-SK-P-875 REV. C 5610-TE-4501 5610-M-420-214 SHT. 3 OF 3 E-2389-10-284 DESIGN PSIG: 2485 OPERATING PSIG: 2235 HYDROSTAllC PSIG: 2335 TEMP(F): 650 TEMP(F): 550 TEMP(F): 547 3

160 UT CAUBRATION BLOCK:

A-376, TP316 SMLS TITLE:

3 CHARGING UNE DATE:26 SEPT. 1988 REVISION APPROVED BY 3

E. L ANDERSON ZONF 45 DRAWING NUMBER:

004-A39

FINAL REPORT OF ZNSERVICE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL'THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX B PERSONNEL CERTZFZCATIONS EXAMINERS NAME

BAKER, ROGER LEVEL III PT UT 10-11-88 METHOD EYE EXAM DATE BRILEY g ROBERT DUBREUIL, RICHARD LAFLEUR, RUSSEL LAKE, EDWARD MC CABE, WILLIAM NOWAKOWSKIg DAN III UT/PT UT/PT UT/PT UT/PT PT UT/PT 11-10-87

, 4-13-88 6-27-88 5-23-88 6-30-88 4-26-88 19

t FINAL REPORT OF INSERVZCE ZNSP TZON NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX C EQUIPMENT CERTIPICATZONS ULTRASONIC EQUIPMENT SERIAL NUMBER 06446E 784519 MANUFACTURER SONIC MARK I SONIC MARK I DESCRIPTION ULTRASONIC FLAW DETECTOR ULTRASONIC FLAW DETECTOR" 20

~

~

FINAL REPORT OF INSERVZCE INSPECTZON NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX D EQUIPMENT CERTZFZCATZONS ULTRASONIC SEARCH UNITS SERIAL NUMBER 021692 021729 AEROTECH

.25 AEROTECH

.25

2. 25 2.25 ROUND ROUND MANUFACTURER SIZE FREQUENCY DESCRIPTION 21

t FINAL REPORT OF'ZNSERVICE ZNSP TZON NONDESTRUCTIVE EXAMZNATZONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX E EQUIPMENT CERTZFZCATZONS ULTRASONIC COUPLANT BATCH NUMBER MANUFACTURER DESCRIPTION 8764 8872 ECHO LABS ECHO LABS ULTRAGEL II ULTRAGEL II 22

FINAL REPORT OF INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX F EQUIPMENT CERTIFZCATZONS SURFACE THERMOMETERS

'SERIAL NUMBER MANUFACTURER DESCRIPTION 1191 1197 87-04 PTC PTC PTC SURFACE THERMOMETER SURFACE THERMOMETER SURFACE THERMOMETER 23

~

~

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 G EQUIPMENT CERTZFICATZONS PENETRANT MATERIAL BATCH NUMBER 87M025 87L071 88E035 MANUFACTURER DESCRIPTION MAGNAFLUX CLEANER SKC-NF-ZC-7B MAGNAFLUX PENETRANT SKL-HF/S MAGNAFLUX DEVELOPER SKD-NF/ZP-9B 24

FZNAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08

'APPENDIX H EXAMINATIONPROCEDURES PROCEDURE NUMBER NDE 3.3 NDE 5.4 REVISION FIELD NUMBER CHANGE 2

N/A

, N/A TITLE LIQUID PENETRANT EXAMINATION SOLVENT REMOVABLE VISIBLE DYE TECHNIQUE ULTRASONIC EXAMINATION OF AUSTENITIC PIPING WELDS NDE 5.19 N/A ULTRASONIC EXAMINATION OF SOCKET WELDS IN PRESSURIZER AUXILIARY SPRAY LINE (PTN 3&4) 25

FINAL REPORT OF ZNSERVZCE ZNSPECT10N NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PZPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX I CALIBRATION BLOCK CALIBRATION BLOCK NUMBER DESCRIPTION 2

DRAWING NO.

UT-44 UT-52

.438 INCH THICK, 3..0 INCH DIA C-4174-019 2.0 INCH DIA. SOCKET WELDED MOCK-UP 26

FINAL REPORT OF INSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO 88-08 APPENDIX J'IQUID PENETRANT DOCUMENTATZON LOG DATA SHEET NUMBER 3.3-288 3.3-304 3.3-287 3.3-281 3.3-286 3.3-290 3.3-285 3.3-291 3.3-284 3.3-289 3.3-283 3.3-342 3.3-341 IDENTIFICATION NUMBER 3"-CH-1401-32 ELBOW 3 "-CH-1401-33 PIPE 3 n-CH-1401-34 ELBOW 3"-CH-1401-35 PIPE 3"-CH-1401-36 ELBOW 3"-CH-1401-37 2"-RC-1410-33 2"-RC-1410-34 DESCRIPTION PIPE TO ELBOW BASE METAL ELBOW TO PIPE BASE METAL PIPE TO ELBOW BASE METAL ELBOW TO PIPE BASE METAL PIPE TO ELBOW BASE METAL ELBOW TO PIPE VLV. 4-313 TO PIPE PIPE TO RED.

TEE 27

t FINAL REPORT OF ZNSERVICE ZNSP CTZON NONDESTRUCTIVE EXAMINATIONS OF UNZSOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN'NO ~ 88-08 APPENDIX K ULTRASONIC EXAMINATIONDOCUMENTATZON LOG DATA SHEET NUMBER 5.4-25 IDENTIFICATION NUMBER 3"-CH-1401-32 ELBOW 3 Ii-CH-1401-33 PIPE 3"-CH-1401-34 ELBOW 3"-CH-1401-35 PIPE 3't-CH-1401-36 ELBOW 3'r-CH-1401-37 DESCRIPTION PIPE TO ELBOW BASE METAL ELBOW TO PIPE BASE METAL PIPE TO ELBOW BASE METAL ELBOW TO PIPE BASE METAL PIPE TO ELBOW BASE METAL ELBOW TO PIPE 28

FZNAL REPORT OP ZHSZRVZCE ZNSPZCTZOH HONDESTRUCTZVZ ZXAMZNATZONS OF UNZSOLABLE PZPZHG SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE HRC BULLETZH HO 88-08 DATA SHEET NUMBER 5'9-1 2"-RC-1410-33 2"-RC-1410-34 VLV. 4-313 TO PIPE PIPE TO RED.

TEE APPENDIX K ULTRASONIC EXAMZHAT1ON DOCUMENTATION LOG IDENTIFICATION DESCRIPTION NUMBER 29

FINAL REPORT OF ZNSERVZCE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX L ENGINEERING RECOMMENDATZONS DOCUMENT NO.

SE&PT-SSAD-7814 30

FINAL REPORT OF INSERVICE INSPECTION NONDESTRUCTIVE EXAMINATIONS OF UNISOLABLE PIPING SYSTEM AND COMPONENTS FOR POTENTIAL THERMAL STRESS EFFECTS REFERENCE NRC BULLETIN NO ~ 88-08 APPENDIX M NRC BULLETIN NO ~ 88-08 NRC BULLETIN NO. 88-08 THERMAL STRESSES IN PIPING CONNECTED TO REACTOR COOLANT SYSTEMS 31

ATTACHMENT 2 Re:

Turkey Point Units 3 and 4

Docket Nos.

50-250 and 50-251 NRC Bulletin 88-08 Thermal Stresses in Piping Connected to Reactor Coolant S stems ITEM 3 Plan and implement 'a program to provide continuing assurance that unisolable sections of all piping connected to the RCS will not be subjected to combined cyclic and static thermal and other stresses that could cause fatigue failure during the remaining life of the

unit,

Response

FPL identified two flowpaths where the concern profile of NRC Bulletin 88-08 is applicable:

0 0

1 ~

Charging pumps to pressurizer auxiliary spray Charging pumps to C Hot Leg.

Flow Evaluation and Com arison A detailed review of the unisolable piping in the two inch auxiliary spray and the three inch charging to the C Hot Leg flowpaths, shows that thermal transients from in-leakage are unlikely to occur for the following reasons:

a)

The differential pressure across isolation valves 310B and 311 is approximately 50

psi, compared to approximately 320 psi across the leakage valve of NRC Bulletin 88-08.

b)

The auxiliary spray and charging flow is delivered, through the regenerative heat exchanger, at 493'F for steady state conditions.

For sufficiently large leakage flow (approximately.5 gpm or more), the flow is expected to remain hot.

Therefore, stratification will not significantly occur as the difference in temperatures between the two fluids will be relatively small.

c)

The piping configurations at Turkey Point Units 3 and 4

for the two flowpaths under consideration tend to minimize the potential for pipe failure related to the phenomenon described in NRC Bulletin 88-08.

For the three inch charging line this is due to the upward routing of the line into the

RCS, as opposed to the

Farley and Tihange piping routing described in the bulletin which are routed downward towards the RCS.

In addition, flow stratification would be less severe in the smaller lines (two and three inch vs. the six inch 'pipe reported in the bulletin) due to larger heat transfer around the pipe circumference.

In an effort to further substantiate the

above, FPL contracted with Westinghouse to perform a hydrodynamic test of actual plant specific geometries.

This test is described below.

H drod namic Testin Westinghouse performed hydrodynamic tests in order to assess the potential for the concerns of NRC Bulletin 88-08 at Turkey Point Units 3 and 4.

The hydrodynamic test simulated the thermal-hydraulic conditions in the flowpaths under review at Turkey Point Units 3

and 4.

The test utilized clear piping, dyed water, and actual plant dimensions.

Temperature differences were simulated by specific gravity variations in water (hot fluid) and sodium bicarbonate (cold fluid).

The geometries for both the two inch and three inch flowpaths were modeled.

The results of the flow tests show that although stratification can occur, no mixing mechanism is present for the, configuration at Turkey Point.

Hence, there is an absence of thermal cycling.

Without thermal cycling, pipe failure is not a concern.

Ins ections and 0 eratin Ex erience a)

The recently completed

NDE, showed no indication of cracks in the most susceptible locations of the unisolable sections of the two inch auxiliary spray and three inch charging lines.

b)

Turkey Point Units 3 and 4 each have over fifteen years of operating experience to date and no failures of the type described in NRC Bulletin 88-08 have occurred.

c)

NDE will also be completed during the next refueling outage for each unit to provide additional support to the conclusions reached by the hydrodynamic testing.

CONCLUSION The applicable flowpaths were examined and the locations most susceptible to in-leakage induced thermal fatigue were identified.

NDE was performed in these areas and no cracks were discovered.

The NDE technique utilized accounts for the observations and enhancements implemented at Farley.

Volumetric examinations were done on both the two inch and three inch piping sections.

A special calibration specimen and procedure were developed to implement the volumetric NDE of the two inch piping section.

Based on the flow evaluation performed, thermal transients from in-leakage are unlikely to occur even if the globe valve leaks.

This is based on the fact that a,mixing mechanism to cause thermal cycling does'ot exist as indicated by the results of the hydrodynamic testing.

The flow evaluation conclusions, in conjunction with the NDE performed on the subject flowpaths, provide assurance that the concerns of NRC Bulletin 88-08 are satisfactorily addressed.

No further actions are required, but NDE will be performed during the next refueling outage for each unit to provide additional support to the conclusions reached by the hydrodynamic testing.