ML18227B519

Submits Attachment a, 1976 Inservice Examination of Class I Components at Turkey Point Plant, Unit No. 3, Final Report

ML18227B519
Person / Time
Site:	Turkey Point
Issue date:	12/31/1976
From:	Florida Power & Light Co
To:	Office of Nuclear Reactor Regulation
References
Download: ML18227B519 (88)

Text

ATTACHMENT A 1976 INSERVICE EXAMINATION OF CLASS I COMPONENTS AT TURKEY POINT PLANT, UNIT NO.

3 FINAL REPORT Abstract:

Manual ultrasonic, manual liquid penetrant, and visual techniques were used in the performance of the examinations.

Thirty-two examination areas were found to have reportable visual indications.

These indications were reported to FPL on Customer Notification Forms (CNF's).

Three examination areas were evaluated by FPL personnel and accepted "as is".

Sixteen examination areas were evaluated and dispositioned by FPL personnel with no further action required.

Thirteen examination areas were di'spositioned, reexamined, and accepted by FPL personnel.

One examination area was found to have reportable liquid penetrant indications.

The indication was reported to FPL personnel on a CNF.

FPL personnel dispositioned the indication, reexamined the area, and found it to be acceptable.

No other reportable indications were observed.

A more detailed discussion of the examinations performed, includ-ing Examination Summary Tables, is outlined in this Attachment.

Further documentation of the examinations is available for inspection at the Turkey Point Plant.

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TABLE OF CONTENTS Page UNIT 3

- FINAL REPORT LIST OF ABBREVIATIONS.

i IiVTRODlJCTION

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1 A.

Examination Areas B.

Summary of Examination Results.

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2 II.

DISCUSSION

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5 A.

Ultrasonic Equipment B.

Recording Criteria C.

Radiation Exposure

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6 III.

NONDESTRUCTIVE EXAMINATION

SUMMARY

TABLE

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7 A.

B.

C.

D.

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Examination Area Identification Column Examination Method Column Indications Columns Remarks Column Table

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LIST OF ABBREVIATIONS ASblE CNF CRT DAC FPL ID in.

ISI ISO Lo NDT PL PR PS PT RCC RGX RHR RTD SIS SwRI UT VT l Engineers American Society of llechanica Customer Notification Form Cathode Ray Tube Distance Amplitude Correction Florida Power 5 Light Company Inside Diameter inch, inches Inservice Examination Line Isometric Drawing Zero Reference'Location Nondestructive Testing Pipe Lug Pipe Restraint Pipe Support Liquid Penetrant Examination Reactor Coolant System Regenerative Heat Exchanger Residual Heat Removal Remote Thermal Detector Safety Injection System Southwest Research Institute Ultrasonic Examination Visual Examination

I.

INTRODUCTIOiV During the november 1976-January 1977 refueling outage, Southwest Research Insti-tute (SwRI) personnel performed nondestructive examinations of selected compo-nents in the Florida Power 5 Light Company's (FPL) Turkey Point Plant Unit 3.

These examinations constituted the third such Inservice Examination (ISI) performed at Turkey Point Plant Unit 3.

A.

Examination Areas The components examined were selected in accordance with the Turkey Point Plant Units 3 and 4 Technical Specifications and with the 1970 Edition, includ-ing the Winter 1970 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code.

Representative samples of the components and/or areas in the following list were examined with nondestructive testing (NDT) techniques:

Pressurizer

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Heater Connections Re enerative Heat Exchanger

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Clamp Restraint

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" 'ain Reactor Coolant System--Loop "B"

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Reactor Coolant Drain Lines--Loops "B" and "C"

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2-in. Remote Thermal Detector--Loops "A," "B," and "C" (Hot Leg) and Loops "A," "B," and "C" (Cold Leg)

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4-in. Pressurizer Safety to Valve 551A, 5518, and 551C 4-in. Pressurizer Spray--Loops "B" and "C" 4-in. and 3-in. Pressurizer Relief Lines 2-in. Auxiliary Spray Line 10-in. Safety Injection System and 8-in. Residual Heat Removal--

Loops "A" and "C" 2-in. Boron InjectionLoops "A," "B," and "C" 3-in. High Head Safety Injection System and 2-in. High Head Safety Injection System--Loop "B" and Crossover 14'-in. Residual Heat Removal--Loop-"C"

5 in. Charging Line--Loops "A" and "C"

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S-in. Charging Line--to Valve 312C

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2-in. Letdown Line--Loop "B"

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2-in. Letdown Line--to Three Orifices 2-in. Seal Injection--Loops "A," "B," and "C" B.

Summar of Examination Results The examinations were performed in accordance with the 1968 Edition of Section III,'ppendix IX, of the ASME Boiler and Pressure Vessel Code and the FPL's Turkey Point Plant Units S and 4 Technical Specifications.

The non-destructive examinations were performed using manual ultrasonic (UT), manual liquid penetrant (PT),

and visual (VT) techniques.

The various examinations were conducted in accordance with standard SwRI NDT procedures which were written to conform to the requirements of the applicable sections of the ASi~lE Boiler and Pressure Vessel Code and the SwRI Nuclear Quality Assurance Program Manual.

A copy of each applicable SwRI procedure is included in Appendix D:

Reportable visual indications were observed on thirty-two examination areas.

These indications were reported to FPL personnel on Customer Notification Forms (CNFs) for evaluation and disposition.

Three examination areas were dis-positioned and accepted "as is". by FPL personnel, sixteen areas required only correction by FPL, and thirteen areas required correction and reexamination by FPL.

In addition, scale settings of eleven piping restraints were recorded and reported to FPL on CNFs.

After evaluation FPL personnel found these scale settings acceptable "as is" for operations.

One reportable liquid penetrant indication was observed.

This indication was reported to FPL personnel on a CNF for evaluation and disposition.

After.

lightly grinding and polishing, this indication was reexamined by FPL personnel and 'found to be within acceptable limits.

FPL personnel performed the evaluations and dispositions, performed re-examinations, and closed all CNFs.

A copy of each closed CNF with FPL's com-ments and reexamination results is included in Appendix G.

Of the twenty-seven piping weldments of various diameters examined by manual ultrasonic techniques, five were found to have insignificant indi-cations; four were found to have insignificant and geometric reflectors; two were found to have geometric reflectors; and one was found to have geometric reflectors and reflectors caused by metallurgical boundary interfaces'o defect indications were observed.

Test data (instrument calibration data and examination results) for exami-nations are recorded on standard SwRI forms.

A copy of each of the instrument calibration records and examination data sheets completed onsite is included in Volume II.

Test personnel were certified in accordance with established SwRI personnel certification procedures and with "SNT-TC-1A," American Society for Nondestruc-tive Testing.

For clarification and ASME Code compliance purposes, it should be emphasized'hat the SwRI test personnel performed "examinations" and were not acting as "inspectors."

As defined in Paragraphs IS-202, IS-203, and IS-224 of Section XI of the Code, an "inspector" is an employee of an insurance company or a State or a municipality who, among other responsibilities, also has the duty to verify the owner's or his agent's certification of an operation in accordance with SNT-TC-lA.

Fle also has the duty of auditing the examination program and requiring requalification of an operator when the inspector has reason to ques-tion the performance of that operator.

The SwRI Quality Assurance and Reliability Engineering Section was repre-sented onsite by the SwRI quality assurance (QA) representative, who was present for the majority of the examination period.

The QA representative performed all appropriate duties as outlined in Section 5.2.1.4, "Onsite SwRI Quality Assurance Activities," of the "Project Plan for the 1976 Inservice Examination of Turkey Point Plant, Unit 3."

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II.

DISCUSSION This section of the report provides a description of the equipment used dur-ing the ISI, the recording criteria applied to the ultrasonic examinations, and a listing of approx'ate radiation exposure levels encountered during the ISI.

A.

Ultrasonic E ui ment 1.

Flaw Detection Instruments.

Sonic FTS Hark I ultrasonic instru-ments were used for the manual ultrasonic (UT) examinations.

The Sonic FTS Mark I flaw detection instruments consist of small, lightweight, portable units, including rechargeable battery/charger packs.

,These battery chargers provide a method of recharging the batteries in the tester, as well as provid-ing alternating current (AC) power directly to the instruments.

Also, by nature of the battery charging system, these instruments maintain constant performance characteristics, even though 100-volt service line voltage typically varies at a plant site.

The devices utilize transistori ed circuits of printed circuit board construction and a cathode ray tube (CRT) for a video display of the test data.

They are capable of being used with either direct contact or immersion testing techniques and can be used for single-or dual-transducer testing.

A list of the Sonic FTS Mark I instruments used for these examina-tions, along with their calibration certifications, can be found in Appendix F.

2.

Transducers.

Various brands,

sizes, types, and frequencies of UT transducers (search units) were used to perform these examinat'ons.

A list of the transducers used for the Turkey Point Plant Unit 3 ISI program, along with their calibration certifications, can be found'in Appendix F.

For informa-tion on the actual transducer used for any specific examination, consult the calibration and data sheets in the copies of the original data.

B.

Recordin Criteria The data taken during the examinations were evaluated in accordance with the criteria in each nondestructive testing procedure. 'or ultrasonic examina-tions of piping, the evaluation criteria (Paragraph 8.0 of SwRI Procedure NDT-600-3, Rev.

28) state that "Any indications producing a response greater than

. 20 percent of the reference level and suspected by the operator to be other than geometrical in nature shall be investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector."

In consonance with these criteria, the following was recorded on the exami-nation record sheets:

If there were no indications observed which were above 20 percent of DAC, "No Recordable Indications" was recorded.

If each 'indication observed

>>as above 20 percent of DAC and less than 50 percent of DAC, "All indications investigated as per Paragraph 8.0" was recorded.

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If some indications observed were bet>>een 20 and SO percent of DAC while others

>>ere above 50 percent of DAC, both of the preceding statements were recorded.

C.

Radiation Ex osure Of fundamental concern to all personnel involved in the ISI was the radiation exposure received during the daily examination activities.

Due to high radiation fields encountered during the examinations, SwRI personnel received excess radiation exposure during the examinations on a cumulative as well as a daily basis.

III.

NONDESTRUCTIUE EXAi'lINATIONSPi0iARY TABLE The Nondestructive Examination Summary Table (Page

13) provides the results of the nondestructive examinations performed to satisfy the ASi~K Section 'XI and the Turkey Point Plant Units 3 and 4 Technical Specifications.

The table lists the examination areas,

methods, and results.

It is divided into sections according to major systems or components and then subdivided to list the actual component,

area, or weld examined.

Several columns are self-explanatory, but the following comments may be helpful in interpreting the data as presented.

A.

Examination Area Identification Column In the column "Examination Area Identification," the weld identification system used by SwRI is the same as that used by Westinghouse during previous examinations, with a few exceptions.

The exceptions are as follows:

(1)

Branch connections are numbered as part of the main run of piping

's opposed to being numbered as the first weld on the branch line.

In general, the branch connections are numbered by adding "BC" to the weld identification of the circumferential weld numerically preceding the branch connection.

1'i'hen more than one branch connec-tion is located between two circumferential welds, an additional digit (-1, -2, etc.) is added for uniqueness.

(2)..In general, piping attachments are numbered by adding a "PL" for piping lug, a "PR" for nonwelded piping restraint, or a "PS" for welded piping support to the circumferential weld numerically pre-ceding the component.

In addition, for pipe supports and restraints previously identified, the westinghouse letter designation follows the above-described identification.

When more than one piping attachment is located between two circumferential welds, an addi-tional digit (-1, -2, etc.) is added when necessary to establish uniqueness.

For example, "2PL-A-2" is the pipe lug following

,circumferential weld No. 2, previously designated as "A" by West-inghouse; and it is the second lug numbered.

(3)

During this ISI a number of accessible lines were verified for the correct configuration of the line and the correct location of weldments and components.

New line isometric drawings (ISOs) were drawn, and the weldments and components were renumbered to follow common practices of numbering with the direction of the flow.

Figures A-16, A-19, A-28, A-39, and A-40 in Appendix A were the ISOs affected during this verification of lines.

A revised ISO of each verified line with a cross reference of weldments and components, between the PSI and this ISI, is incorporated in this report.

B.

Examination liethod Column 1.

Visual (VT)

Areas requiring VT were classified as follows:

Piping restraints were examined in accordance >>ith SwRI Proce-dure NDT-900-4, Revision 10.

This procedure includes the guide-lines outlined in Section XI and specifies methods of documenting indications.

,The remaining nuclear power plant components requiring VT were examined in accordance with SwRI Procedure NDT-900-1, Revision 22.

This procedure also includes the guidelines outlined in Section XI and specifies methods of documenting indications.

2.

Li uid Penetrant (PT) hfanual PT examinations were performed in accordance with SwRI Procedure NDT-200-1, Revision 22, using a visible redye penetrant.

Liquid penetrant material certification sheets are included in Appendix F.

3.

Ultrasonic (UT)

The specifics of UT procedure NDT-600-3, Revision 28 (>>ith Deviations 1

and 2) employed in the examinations covered by this report are detailed in Appendix D.

Nelds were subjected to examination scans discussed in the following t subsections.

Exceptions to these tests were usually due to area/component configurations and/or inaccessibility.

a.

Lamination Scan (O'L).

A 0-deg longitudinal wave was used to examine the base metal adjacent to the welds to. determine the existence of any. laminations or inclusions which, if present, would cast "shadows" which could prevent sound beam access to all or part of the welds and/or could offset the interpretation of weld examination results

[see Paragraph IY-344(c) of Ap-pendix IX to Section-III],

b.

Longitudinal Nave Neld Scan (0'ii'). 'n cases where the physical configuration prohibits shear wave examinations from one of the two sides of the weld, a 0-deg longitudinal wave examination was performed from the surface of the weld.

These examinations are consistent with the require-ments of Paragraph IX-342 of Appendix IX to Section III and are used to deter-mine the existence of any reflectors in the weld positioned parallel to the surface of the weld.

c.

Shear ii'ave Scans (45', 45'T, 60').

Each weld was examined using 45-and 60-deg shear

>>aves to determine the internal characteristics of the weld metal and,,

when required, the adjacent base metal for one thickness beyond the edge of the weld.

Examinations were performed from both sides of the weld, >>henever possible, using the required test angles.

In addition, a transverse scan (applied along the weld to detect any reflectorS oriented "transverse to the >>eld") using a 45-deg shear

>>ave search unit was also performed, whenever possible.

C.

Indications Columns The four columns under the general heading of "Indications" are "No Record-able," "Insignificant," "Geometric,"

and "Other."

The results for the VT and manual PT examinations are indicated by an "X" in the appropriate column to be either "No Recordable," "Insignificant," or "Other."

VT examinations were performed in accordance with the guidelines of Paragraph IS-211 of Section XI.

For visual indications, the term "Insignificant" was applied when minor surface irregularities were observed.

The term "Other" was used to describe the indications which were deemed reportable to FPL personnel for evaluation and/or disposition.

l1anual PT examinations were performed 'and the results were evaluated in accordance with the requirements of Articles 3 and 6 of Section III of the ASi~K Boiler and Pressure Vessel Code.

For these examinations, the term "Other" was used to describe indications which were deemed

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reportable to FPL personnel for evaluation and/or disposition.

The results for the manual UT examinations are indicated by recording the angle of the ultrasonic search unit (see Paragraph II.B.3 above) under the column heading which describes the test, results for that angle, i.e., the "No Recordable," "Insignificant," "Geometric," or "Other" column.

In the perfor-mance o

the UT examinations, the data recording level was established by SwRI procedur'e NDT-600-3, Revision 28.

Generally, the recording level for manual UT examinations of piping is 50 percent of the DAC Curve established during instrument'calibration, and the recording level for manual UT examinations of pressure vessels is 20 percent of the DAC when the configuration and acoustic properties of the vessel or area permit.

Specifically, The term "No Recordable" was applied when no-indications were observed or when the amplitudes of the indications were below the recording level that SwRI procedure NDT-600-3, Revision 28, specifies'Insignificant" was applied when the amplitude of any indication was equal to or greater than the recording level that SwRI proce-dure NDT-600-3, Revision 28, specifies but less than 100 percent of DAC.

"Geometric" indications are those indications which have an ampli-tude equal to or greater than 100 percent of the DAC and are general-ly resolved as due either to "root" geometry, "crown" geometry, "inside surface" geometry, or "outside surface" geometry.

An indication due to "root" geometry is one in which the ultrasonic wave is reflected by the root geometry of the weld bead; crown geometric indications occur when the ultrasonic wave reflects off the inside surface of the examination area, strikes the crown of the

weld, and is returned to the transducer;

."inside surface" geometric indications occur when the internal surface of the examination area or the weld fitup contains an angular plane sufficient to reflect a

portion of the ultrasonic beam back to the transducer; and "outside

. surface" geometric indications occur when the ultrasonic wave reflects off the inside surface of the examination

area, strikes the roughness of the outside of the examination area, and is returned to the transducer.

Figure 1 illustrates a typical "crown" indication and Figure 2 illustrates a typical "root" indication.

The "Other" indications include those which have had an, amplitude equal to or greater than 100 percent of the DAC and were not included in the column of "Geometric" indications, as described above.

Also, if'any indications existed such as Code-acceptable laminations or artifacts, they would have been 'included in this column.

D.

Remarks Column to the examination results:

1&en complete coverage of the examination area was.not possible, the "Remarks" column was used to indicate the limitations.

For VT or manual PT examination results reported in the "Other"

column, a brief description is given in the "Remarks" column.

For ultrasonic examination results reported in the."Other" column, a brief description of the resolution of the indications is per-sented in the "Remarks" column.

Reference is made in the "Remarks" column to CNFs used in the reporting of indications.

CNFs were also used to report to FPL personnel the scale settings on pipe restraints,'nd these are included in the remarks column.

Table (See Pages 15 throu h 48) 10

FIGURE 1

Pictorial Representation of Crown Indication Fz~g@< g g.~W)'p L

FIGURE 2 Pictorial Representation of Root Indication

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TURK'EY I'OINT I'LANT UHlT 3 1976 iHSL'RVICE IIXISIIHATlOHSUMIARY OF HOHDESTRUCTIVL'XiQIIHATIOHS

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PRFSSURI ZER Scc Ai ondix A Fi uros A-2 and A-3 ASME ASME SEC. XI SEC. XI ITEMNO CATGY.

EXAh'IINATION AAEAIDENTIFICATION Swill WELD

'IIOCEDUA EXAM.SUhI NO.IAEV.

SHEET NO.

NO IIECORDAULE INDICATIONS INSIGNIFICANl GEOhIETAIC OTHER

- BEhIARKS 2.4 P.-2 llcatcr Connections Hos.

1 through 78 VT 900-1/22 300099 V4

TURKEY,POINT PLANT UNIT 3 1976 INSERVICE EXAIIINATIONSUIIhIARY Ol'ONDFMRUCTIVE EXAHINATIONS REGENERATIVE lllPAT EXCIIANGER Sco A i cndlx A Fi nre A-S ASME ASME SEC. XI SEC. XI ITEMNO CATGY.

EXAMINATION AIIEAIDENTIFICATION Swfll WEhP MCTIOD '"

NoanEV.

SIIEETNO.

INDICATIONS NO AECOIIDABLE INSIGNIFICANl GEOMETIUC OTIIEII IIEMARKS RGX-(I)-CR Clamp Restraint VT 900-4/10 300056

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'fUIIREY I'OINT I'LANT lfNIT 3 1976 IHSEltVICL'XIOIIHATIOIISUFSIA1tY OF HONDESTRUCfIVE I!XIQIINATIONS IIIQCfOlt COOIANIll'INGI&l'8" (Seo Appendix A, Figurc A-7)

ASME ASME SEC. XI SEC. XI ITEMN CATGY.

EXAMINATION AREA I DE NTI F ICATION EXAM.

METHOD SwAI WELD AOCEDUAI EXAM.SUM NO.IAEV.

SHEET NO.

NO AECOAOAOLC INDICATIONS INSIGNIFICAN GEOMETAIC OTHEA REMARKS 29" ID IICC-(8)-2 Pipe-to-Pipe 900-1/22 300157 600-3/28

w. dev.

I 8 2 0 I,45 T 45 45 60 hrc Strike.

Scc CNF 4100369.

Rcmovcd by lifht polishing.

Reex-amination was pcrformcd by FI'I.

personnel.

Three 45'ndications duc to crown geometry.

Two 45'nd two 60 in-dications duc to metallurgical intcrfacc.

Scc Indication ltcso-lutlon Record 4310009.

Cal. Std. Tp-hlRCL-2.437-SS-13.

3.3 RCC-. (8) -4 Elbow-to-Hozzle VTIr Iff 900-1/22 200-1/22 600<<3/28

w. dcv.

I fj 2 300135 X

X 0 L,O W,45 45 T,GO Ho examination from thc downstream side due to thc nozzle configurat-ionn.

Ho examination from thc up-stream side from 0" to 20" due to stcam generator support str1icturc.

Examination limited to 4-3/8" in "N" from the upstream side duc to elbow taper.

Ca. Std. TP-IlRCL-2.437-SS-I3.

31" ID 3.3 ltCC-(8)-5 Nozzle-to-Elbow Vf PTIlr 900-1/22 200-1/22 600-3/28 w, dcv, Ifj2 300136 X

X 0 LIO N045 0

45'T,60 Ho oxamlnation from thc upstream side duc to the nozzle configura-tion.

Examination limited to 4-1/2" in "II" from thc downstream side duc to elbow taper.

Cal.. Std, TP-IIRCL-2.437-55-13.

TURKEY I'OINT PLANT UNIT 3 1976 INSI!RVICI) L'XAIIIHATIOHSU)l)ARY OF NOH))IW'RUCTIVI! I!XA)IIHATIONS 2"

RC l)RAIN I.INI! LOOI'0" See A) endix A Pi uro A-10 ASMC SEC. XI ITEh) NO ASME SEC. XI CATGY.

EXAMINATION Af)EA IDENTIFICATION EXAM.

METIIOD SwAI WELD ROCEDUR EXAM.SUh)

NO7REV S))EET NO.

NO RECORDABLE INDICATIONS INSIGNIFICANl GEOMETRIC OTIIE0 RE)IARKS 4.8 4.6 J-I K-2 G

Valve-to-Pipe 6-PR Pipo Restraint VT PT 900-1/22 '00029 200-1/22 900-4/10 3000B9 X

X Scale rcadina:

Indicator at lock bolt hole lovel.

Scc CNF S)00355.

'Acccntcd "as is" hv Fl'I. ncrsonnel.

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TURKfY I'OINT PLANT UNIT 3 1976 IHSPRVICP. EXAMINATION SUMIARY OP HONOIBTRUCTIVC PXAIIIHATIONS 2"

RC DRAIN I.INE IA)OP "C" (See A

endlx A, Piyire A-II)

ASME SEC. XI ITEhINO ASME SEC. Xl CATOY.

EXALIINATION AREA IDENTIFICATION ROCEDUR SwRI LIETHOD WELD EXAhI.SULI SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICANT GEOMETRIC OTHER RELIARKS 4,8 J-I 6

Valve-to-PIpe 000-1/22 200-1/22 Zn0021

TURKEY I'OINT PLANT UNIT 3 197G INSERVICE EXAHINATIONSI08fhRY OF NONDESTRUCTIVE EXQIINATIONS 2"

RTII IIOT IJ!G IQOP nAn Sec A~ cndix A Fi ore A-15 ASME SEC. XI ITEMNO ASME SEC. XI CATGY.

EXAMINATION AAEAIDENTIFICATION SwAI EXAM.

'AOCEDUA NO.IAEV.

WELD EXAM.SUM SIIEET NO.

I NO I GATI 0 NS NO AECOADAOLE INSIGNIFICANl GEOMETAIC OTIIEA REMARKS 4.G I;-2 IO-PR-0 Pipe Rcstr'aint VT 900-4/10 3000GS Scale reading at lock holt hole level.

Sce CHF II00348.

Accepted "as is" by FPI. Personnel.

4.8 4.8 J-I J-I 19 Tco-to-Pipe 32 Tcc-to-Pipe VT PT VT PT 900-1/22 200-1/22 900-1/22 200-1/22 300027 300028

CO TURKEY POINT PLAIIT UNIT 3 1976 IHSERVICE EXAhllHATION SUhk!ARY OF NONDESTRUCTIVE EXAIIIHATIONS 2" RTI) IIOT LEG IXSP "0" See A )cndix A Fi urc A-16 ASME ASME SEC. XI SEC. XI ITEMNO CATGY.

EXAhIINATION AIIEAIOENTIFICATION SnRI WELD

'AOCEOUA EXAhl.SUM NO.IAEV.

SIIEET NO.

NO nECOnOAELE INDICATIONS INSIGNIFICAN'I GEOAIETAIC OTIIEII REMATIKS 4.8 4 '

4.8 7

Pipe-to-Valve 12 Coupling-to-Pipe 15 I'ipc-to-Elbow 20 Pipe-to-Tce VT PT VT PT Vl'T Vl'T 900-1/22 200-1/22 900-1/22 200-1/22 900-1/22 200-1/22 900-1/22 200-1/22 300066 300005 300006 300007 4 ~ 4 4.6 G-2 K-2 238L Flange Bolting 30-PR-A Pipe Restraint VT 900-1/22 300137 VI'00-4/10 300067 Eight bolts and sixteen nuts examined in place.

1/4" space between U bolt ahul pipe.

Sce CHF 1100344.

Shims werc added by I'I'I. pcrsonncl.

4,8 31 Pipe-to-Coupling 900-1/22 200-1/22 300012 4.6 K-2 33-PR-C Pipe Restraint VT 900-4/10 300011

TURKEY POINT PLANT UNIT 3 19m INSERViCB BXANINATIONSIDDIARY OF NONDESTRUCTIVE I:.KAIIINATIONS 2" RTI) IIOT IJ!G I.OOP "C" Scc A

endix A Fi uro A-D ASME AShIE SEC. XI SEC. XI ITEMN CATGY.

EXAMINATION AAEAIDENTIFICATION SwAI WELD

'AOCEDUA EXAM.SUh'I NOJAEV.

SHEET NO.

NO AECOADADLE INDICATIONS INSIGNIFICAN1 GEOMETAIC OTHEA AEhIAAKS 4.8 4.8 4.8 4.4 K-2 Elbow to-Pipe 14 Pipe-to-Valve 19 Flange-to-Pipe 19DL Flange Dolting 2G-PR-D Pipe Rostraint 900-1/22 300022 200-1/22 900-1/22 300010 200-1/22 900-1/22 300089 200-1/22 VT 900-1/22 300138 VT 900-4/10 300068 Bight bolts and sixtocn nuts examined in place.

U bolt bracket bent and mis-aligned with holdor.

Scc CNF k100341.

U bolt was aligned nnd holder tightened by FPL pcrsonncl.

4.8 4.8 J-I'8 I'ipc-to-Elbow 34 I ipe 'to Tee 900-1/22 300018 200-1/22 900 I/22 300100 200-1/22 X

X

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TUIIKEY I'OINT I'LAtffUNIT 3 1970 \\NSEIIVICE I!XISIINA'flOttSINIILAIIYOF t)ONQIISTNlCTIVIIPXAIIIIIATIONS 0 Cnl.n AShlE AShlE SEC. XI SEC. XI ITEMNO CATGY.

.I!B IA)QP u "

Se EXAMINATION ABEAIDENTIFICATION

- 8 SwBI WELD

'BOCEDUBI EXAM.SUM EXAM.

NOJBEV.

SIIEET NO.

NO BECOBDADLE INDICATIONS INSIGNIFICAN)

GEOh)ETBIC OTIIEB BEhlABKS 4.8 4.8 J-I J-1 13 Pipe-to-Coupling 28 Pipe-to-Valve Vf PT Vf PT 900-1/22 300059 200-1/22 900-1/22 300023 200-1/22 4.8 J-I 38 Pipe-to-Elbow VT 900-1/22 300024 PT 200-1/22

2" RTA COI.D TURKEY POINT PLANT U>>1T 3 1976 i>>SERViCB BKANI>>ATlO>> SeSIART OF >>0>>IIImnUCT1VB FXAW1>>AT10>>S

.EG tare n8>>

Sce A

andix A

Fi uro A-19 ASME ASME SEC. XI SEC. XI ITEMNO CATGY.

EXAMINATION AREA IDENTIFICATION.

EXAM.

METHOD SwAI WELD AOCEDUA EXAM.SULI NOJAEV.

SHEET NO.

NO AECOADADLE INDICATIONS INSI G >>IF I CANl GEOMETAIC OTHER AEMAAKS 4.8 4.6 4.8 4.6 K-2 K-2 5

Pipe-to-Plbow 7-PR-8 I'lpe Restraint 8

Elbow-to-Pipe 17-PR-B Pipo Restraint VT PT 900-1/22 300062 200-1/22 900-4/10 300139 9DD-1/22 300063 200-1/22 900-4/10 300064 Broben restraint.

Sce C>>F l100340.

Restraint was repaired by APE personnel.

4.8 4.4 G-2 18-L'lbow-to-Pipe 228L Flange 8olting Vf PT 900-1/22 300035 200-1/22 900-1/22 300140 Bight bolts and sixteen nuts ex-amined in place.

4.8 4.8 J-1 25 Pipe-to-Tee 28 Tce-to-Pipe Vf PT 900-1/22 300032 200-1/22 9DD-1/22 300004 200>>1/22

i4

~

'unfrV POINT Pmrr IINIT 3 1976 INSFIIVICE EXAlllNA'flONSIIWIAIIY OP NONIIfMIIUCflYf:IIXAIIlNATlOILS 2" RTB COI.D IlIG lOOP "C" Sco A >)endix A Pi ure A-20 AShIE ASh1E SEC, XI SEC. XI ITEh1NO CATGY.

EXAh1INATION ABEAIDENTIFICATION EXAM.

METIIOD SwBI WELD

'BOCEDUB EXAM.SUM NO IBEy.

SIIEET NO NO BECOBDAELE INDICATIONS INSIGNIF ICANT GEOMETBIC OTIIEB BEhIABKS

~I ~ 8 8.8 z.s 4.8 J-1 J-1 J-1 J-1 2

Pipe-to-Elbow 5

Valve-to-Pipe 15 flbow-to-Pipo 29 Elbow-to-Pipe 36 Pipe-to-Reducer VT P.T VT PT 900-1/22 300008 200-1/22 900-1/22 300009 200-1/22 900-1/22 300026 200-1/22 900-1/22 300019 200-1/22 900-1/22 300020 200-1/22

TURKEY POINT PIJQIT UNIT 3 197G IHSIIRVICE IIXNIIHATIOHSIMIARY OF HOHI)PM'IUN."fIVIII!XANINATIOHS 4" I'RESSURIZIIR SAFIITY TO VAI.VI! 551A (Scc Appendix A," Figurc A-22)

ASME SEC. XI ITEh1NO ASME SEC. XI

~ATGY.

EXAMINATION AREAIDENTIFICATION EXAh'I.

hIETIIOD SvrAI

'ROCEOURI NO.IREV.

IVELD EXAhl.SUM SIIE ET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN1 GEOMETRIC OTIIER REhIARKS 4.1 4.2 J-I lA Hottlo-to-Safe-End 7

Pipe-to-Pipe VT PT UT 900-1/22 200-1/22 600>>3/28

w. dcv.

1 f,2 900-'1/22 G00-3/28 M, dcV 1 6 2 300141 300013 X

X O'L,O',45'5 T,60 X

0 1.,45 45 T,60 Ho examination fron thc upstream side duo to tho nettle confitprration.

Cal. Std. TP-4-120-.438-SS-4.

Cal. Std. TP-4-120-.438 I.

TURKCY POINT PLANT UNIT 3 1976 INSERVICE EXANINATION SUIIIARY OP NONDESTRUCTIVL'XAhllNATIONS 4" PIUCSSURIZfR SAFI!1Y-TO VAI.VE 5518 Seo A )cndix A Fi uro A-23 ASME SEC. XI ITEMNO ASh'IE SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION

'AOCEDUA SwAI hIETIIOD NO.IAEV.

'IVELD EXAhl.SUM SIIEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN1 GEOMETAIC OTIIE AEhlAAKS 4.2 J-I I

Elbow-to-Pipe 900-1/22 600-3/28

w. dov.

142 300014 X

O'L,45'T,60'5 Onc 45'ndication duc to crown geometry.

Sco Indication Resolution Record l310007.

Cal. Std. TP-4-120-.438-SS-4.

TURKEY POINT PLANT UNIT 3 1976 INSEIIVICP. PXAhllHATIOH SUI&lhftY OF HONDIBTRUCTIVL'XAIIINATIOtIS 4" PRIISSURIZIIR SAFFTY TO VALVE 551C (Sco Appendix A, Fipurc A-24)

ASME SEC. XI ITEMN ASIAE SEC. XI CATGY.

EXAMINATION AAEAIDENTIFICATION SwAI AOCEOIjAI NO.IAEV.

'LVELD EXAM.SUM SIIEET NO.

It<OICATIONS NO AECOAOABLE INSIGNIFICAN GEOMETAIC OTIIEA AEMAAKS 4.2 J-I 5

Pipe-to-flboM 900-1/22 600-3/28 wo dove I

Pj 2 300015 X

041.,454, 45'T,60 Col. Std. TP-4-120-.438-SS-4.

2~

M TURKEY I'OINT PihttT UNIT 3 1976 IttSL'RVICE EXANINATIONSQIIIARY OP ttOIIAESTRUGfIVE I!XAIIlttATIOIIS

~,

4" PRESSURIZER SI'RAY LOOP "8" (Sco Appendix A, Figuro A-25)

ASME SEC. XI ITEhINO ASME SEC. XI CATOY.

EXAMINATION AREA IDENTIFICATION Swnl

'AOCEDUAI NOJAEV.

WELD EXAM.SUhI SNEET NO.

INDICATIONS NO AECOADABLE INSIGNIFICANl GEOh'IETAIC OTHEA nEMAnKS 1.2 1.G K-2 9

Iitbow-to-Pipe 9-PR-C Pipe Restraint 900-1/22 600-3/28 w

dev, Itj2 Vr 900-4/10 300156 300090 0 L,45 45 T,60 Ho examination upstream from 1-3/4" to 7-1/8" duc to elbow curvature.

Cal. Std. TP-4-120-.438-SS-4.

Angle iron restraint misaligncd.

Sec QIP t100343.

Acccptcd "as ls" by FPI. personnel.

4:6 K-2 12-PR-F Pipe Restraint Vf 900-4/10 300091 Angle iron restraint mlsaligncd.

Sco QIP f100342.

Acccptcd "as is" hy PI'I. personnel.

4.G K-2 13-PR-G Pipe Restraint Vl'00-4/10 300092 X

ScAle roading: 0u.

Scc QIF l100349 ~

Acccptcd "as is" hy PI'I. pcrsonncl.

K-2 15-PR Pipe Restraint Vf 900-4/10 300093 Scalo reading:

4-7/8".

Scc QIF I100351 ~

Accepted "as is" by FPL pcrsonncl.

4.6 K-2 16-PR Pipe Restraint Vr 900-4/10 300094

'lllltKI<Y POIIff PIJQff UNIT 3 1976 IHSERVICB IIXAIIIHA'fION SUWIAIIY OF NQIUESTRUCfIVU RXAIIINATIOHS 4" PIIPSSURIZEII SPItAY IAXIP "C" Sce A

cn<lix A Fi ure A-26 ASME SEC. XI ITEMNO ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD Swnl ROCEDUR NOJREV.

WELD EXAM.SUM SIIEETNO.

NO RECORDABLE INDICATIONS IN S IGNI F I CAN1 GEOMETRIC OTIIER REMARKS 4.2 4.6 4.2 4.2 K-2 K-2 K-2 K-2 2-PR-I I'ipc Restraint 2-PR-2 Pipe Restraint 8

lllbow-to-Pipe 8-PS-D Pipe Support Structure 10-PR-J I'ipe Restraint 13 Pipe-to-flbow 18 Valve-to-Pipe 900-4/IO 900-4/10 900-1/22 00-3/28

.dev.

I f< 2 00-4/10 00-4/10 00-1/22 00-3/28

. dcv.

I f>2 00-1/22 00-3/28

. dcv.

I 8 2 300095 300096 300142 300031 300097 300143 300017 O'L,45'5'T,60L,45'5'T,60' O'I.,O'II,45'5'T,60'cale reading: 2-1/4".

Scc CNI u 100356.

Accepted "as is" by FPI. pcrsonncl.

Scale reading: 3-1/4".

Scc CHF I100350.

Acccptcd "as is" l>y FPL personnel.

Arc strikes,

gouges, and grind-ing marks.

Sec CHF el00372.

Indications removed by grinding.

Reexamination was performed by FPL personnel.

Ho examination from thc upstream side from 10-1/2" to 12-12" duc to thc elbow inner radius.

Cal. Std. TP-4-120-.438-SS-4.

Scale reading: 3".

Scc CNF S 100353.

Accepted "as is" by FPI. pcrsonncl.

Arc strikes:

Scc CNF I100373.

Indications removed by grinding.

Rccxamination was pcrformcd l>y FPL pcrsonncl.

Cal. Std. TP-4-120-.438-SS-4.

No examination from the upstream side due to thc valve configuration.

Ho examination from thc downstream side from 5" to 12" duc to thc elbow inner radius.

Cal. Std. TP-4-120-.438-SS-4.

O.

TURKEY POINT I'I&ITUNlT 3 1976 INSBRVICB BXAIIINATIOHSUIIIiARY Ol'ONDESTRUCTIVE IIXi@IIHATlOHS 0,

4" I'RBSSURIZBR RBLlEF'ec A endix A Fi urc A-27 ASME SEC. XI ITEMNO ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXAhl.

METHOD SwRI

'ROCEDUR NO.IREV.

WELD.

EXAM.SUhl SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICANT GEOMETRIC OTHER REhIARKS 4.2 4.6.

4.6 K-2 K-2 1A Nozzle-to-Safe Bnd 3

Elbow-to-Pipe 7-PS Pipe Support Structure 8-PS-1 Pipe Support Structure VT 900-1/22 200-1/22 600-3/28

w. dev.

1 f(2 900-1/22 600-3/28

w. dev.

I f(2 900-4/10 900-4/10 300144 300155 300101 300102 X

X

'.,O'II,45, 45'T,60 0 L,45 T 45'0 No examination from the upstream side due to thc notxlc configuration.

Cal. Std. TP-4-120-.438-SS-4.

Arc strikes,

gouges, and wcl'd spatter.

See CNF f100380.

Indications rc-movcd after grinding.

Reexamination was pcrformcd by I'Pl, personnel.

Two indications due to crown geometry.

Scc Indication Resolution Record g310006.

Cal. Std. TP-4-120-.438-SS-4.

Pipe support structure disconnected.

Scc CHF I100368.

Support rcconncctcd by FPI. pcrsonncl.

Pipe support structure disconnected.

Sce CHF I100363.

Support rcconnccted by FPI. pcrsonncl.

TUIIXfY POINT PLANT UNIT 3 197G IHSI0IIVICf.'XAIIIHATIONSUIIIIARY OF HOHDISTIIUCTIVf: EXQIIHATIOHS 3" PRI0SSURIZER RELIEF (Sec Appendix A, Figure A-27)

ASIAE SEC. XI ITEMNQ ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD S00B I

'AOCEDUA NO.IAEV.

WELD EXAM.SUM SI IE ET NO.

INDICATIONS NO AECOBDAGLE INSIGNIFICAN1 GEOh'IETBIC OTIIEB AEMAAKS 4.2 4 ~ 2 2

Elbow-to-Elbow 8

Elbow-to-Elbow 900-1/22 600-3/28

w. dov.

1 f02 900-1/22 600-3/28 wo deva 1 F02 300145 300154 O'L,45',

45 T060' L04545'T,60'rc strikcs0 gougcs0 and wold spatter.

See CHF 1100370.

Indications rcmovcd after grinding.

Reexamination was performed I>y FI'L personnel.

Cal. Std. TP-3-1G0-.438-SS-2.

Are strikes,

gouges, and wold spatter.

Sco CNF 0100371.

Indications rcmovcd after grinding.

Rccxamination was performed by FPL personnel.

Cal. Std. TP-3-160-.438-SS-2.

TURKIIY I'OINT PIJQIT UNIT 3 1976 IHSERVICL EXANINATIOH SIWIARY OF NONI)ESTRUCTIVE EXAIIIHATIONS 2" AUXILIARYSPRAY I.IHB (Sce Appendix A, Figurc A-28) 0, ASMC ASME SEC. XI SEC. XI ITEh1NO CATGY.

EXAMINATION AAEAIDENTIFICATION EXAM.

METHOD SwfU WELD

>AOCEDURI EXAM.SUM NO./IIEV.

SHEET NO.

NO RECOIIDAOLE INDICATI0 NS INSIGNIFICAN GEDMETRIc QTHEA AEh1ABKS 4 6 K-2 4-PR-S Pipo Restraint 900-4/10 300103 Scalo reading:

7-1/2".

Scc CNF I100365.

Acccptcd "as is" l>y Fl'I. personnel.

4.6 4.G K-2 K-2 6-PR Pipe Restraint 8-PR Pipe Restraint 900-4/10 300050 900-4/10 300049 Scale roading:

2".

Sco CHF 8100352

ccepted "as is" by I'I'I. Personnel.

4.G K-2 13-PR-N Pipe Rostraint 900-4/10 300048 Scalo reading:

3/4".

Sec CNF f100354 ~

Accepted "as is" l>y Fl'L ncrsnnnel.

4.8 14 Pipe-to-Elbow Vf PT 900-1/22 300057 200-1/22 Linear indication.

Sce CHF II00357.

Indication removed by light grinding and polishing.

Reexamination was performed by FPI. Personnel.

4.8 4.6 K-2 19 Elbow-to-Pipe 20-PR-ll I'ipe Restraint 900-1/22 300061 200-1/22 900-4/10 300104 X

X U bolt untightencd.

Sec CHF 8100362.

U bolt was replaced by FPI, personnel.

4.8 30 Pipe-to-Elbow VT PT 900-1/22 300105 200-1/22

TURKEY I'OINT PIJQA'IHIT 3 1976 ItISERVICB EXAh!IHATIOIISIWIARY OP HOHDESTRUCTIVE EXAhIIIIATIOHS 0'~ SrS AHD S" RIIR IDOI'"

Soe

)

. il I

o 9

ASME ASLIE SEC. XI SEC. XI ITEMNO CATGY.

EXAMItIATION AIIEAIDENTIFICATION SwRI WELD

'ROCE DUB EXAtiI.SUII NO.IAEV.

SHEET NO.

NO AECOADADLE INDICATIONS INSIGNIFICANl GEOAIETRIC OTIIER AfMAIIKS 4 6 K-2 6-PR-A Pipe Restraint VT 900-4/10 300036

03 TUIU'I!Y I'OIIflLuffUNIT 3 l976 rNSERVlCE I:.mlrNAnON SueIARY OP NONDIarRUCnVr: rXIUIiNAVTOZS 10" SIS AND 8" RIIR LOOI'C" (Seo Appendix h, Figure A-3l)

ASME ASI'IE SEC. XI SEC. XI ITEMNO CATGY.

EXAMINATION AREA IDENTIFICATION EXAh'I.

METIIOD SwRI WELD ROCEQURI EXAhI.SUM NOJREV.

SHEET NO.

NO RECORDABLE UJDICATIONS INSIGNIFICANT GEOhIETRIC OTHER REhLARKS 4.G "K-2 8-PS-D Pipe Support Structure 900-4/10 300037

TURKEY POINT PLAIIT UNIT 3 1976 INSERVICE I!XANINATIOHSQRIARY OF iHONOESTRUCTIVE I!XiQIIHATIONS 2" IIOROH IHJI!CTICKS Il!OP "A" (Sco Appendix A, PISnro A-32)

ASME AShIE SEC. XI SEC. XI ITEMN CATGY.

E'XAMINATION AREA IDENTIFICATION EXAM.

METIIOO SwAI YIELD

'AOCEDUA EXAM.SUM HOJAEV.

SIIEET NO NO RECORDABLE INDICATIONS INSIGNIFICAN GEOMETRIC OTIIEA AEhIAAKS 4'

J-I 16 Pipe-to-Elbow VT PT 900-1/22 300106 200-1/22 4.6 K-2 IG-PR-I Pipe Restraint 900-4/10 300085 Restraint bent.

See CHF ll00315.

Acccptcd "as is" by I'Pl. pcrsonncl.

4 ~ 6 4.G 4 '

4.8 4.6 K-2 K-2 K-2 K-2 20-I'R-J I'ipo Restraint 20-PR-K Pipe Restraint 24-PR-3 Pipe Restraint 27 Valve-to-Pipe 31-PR-II Pipe Restraint 900-4/10 300038 900-4/10 300039 900-4/10 300051 900-1/22 300107 200-1/22 900-4/10 300052 X

X

W TURKILY I'OINT PLANT UNIT 3 19VG INSEWICE I:.meIINATION SUhIIIAIIY OP NONDFarRUCTIVI:. EXAIIINATIONS 2" DORM INJI.:CTICN lAMP wlV'Seo AppcIidix A, Hero A-33)

ASME ASME SEC. XI SEC. XI ITELINQ CATGY.

EXAMINATION AREA IOENTIFICATION SwAI

'IVELO M

BOCEOUAI EXAM.SUM NO.IAEV.

SIIEET NO.

NO AECOROADLE INDICATIONS INSIGNIFICANI GEOh'IETAIC OTIIEA REMARKS 4.8 4.8 4.8 J-1 J-I J-I J-I 4

Pipe-to-Elbow 8

Pipe-to-Elbow IG Pipe-to-Elbow 28 Pipe-to-Elbow 900-1/22 300108 200-1/22 900-1/22 300109 200-1/22 900-1/22 300110 200-1/22 900-1/22 300111 200-1/22

. X X

X X

'11IRKEY I'OINT PLANT UNIT 3 1976 IHSERVICF. EXAHlHATIOHSUtl!ARY OF HOHI)FSTRUCTIVI! EXi5IIHATIOHS 2" IIORON IH.IIH."I'IOH I.OOP "C" (Sco Appendix A, Figuro A-34)

ASME SEC. XI ITEMNO ASh'IE SEC. XI CATGY.

EXAMINATION AAEAIDENTIFICATION EXALI.

METIIOD SwRI

~

'AOCEDUII NOJIIEV.

WELD EXAhl.SULI SIIEET NO.

INDICATIONS NO IIECOADAOLE INSIGNIFICAN1 GEOMETRIC OTIIE8 REMAIIKS 4.8 4 ~ 8 K-2 4

Pipe-to-Ell>ow 9

Elbow-to-Pipe 14-PR-E Pipe Rostraint Vl'T Vf PT 900-1/22 200-1/22 900-1/22 200-1/22 900-4/10 300112 300113 300086 Pipo not secured by U bolt.

Scc

'HF r100338.

U bolt was rcplaccd by Fl'I. pcrsonncl.

4.8 4.8 22 Pipe-to-Elbow 29 Valve-to-Pipe Vl'T PT 900-1/22 200-1/22 900-1/22 200-1/22 3001'14 300115 Arc striko.

Scc CHF I100377.

Indication was rcmovcd by light grinding.

Rcoxamination was performed by FPL pcrsonnol.

TURKL'Y POINT PLANT UNIT 3 1976 INSL'RVICP. IIXAIIIHATIONSIWIARY OF NONDESTRUCTIVE EXAIIIHATIONS 3" IIIQI IIEAU SIS (Sce Appendix A, Figure A-35)

~,

ASME SEC. XI ITEhl NO ASME SEC. XI CATGY.

EXAMINATION AAEA I DENT IF ICATION Swnl EXAhl.

AOCEDUA METHOD NO IAEV WELD EXAhLSUM SIIE ET NO.

INDICATIONS NO AECOADABLE INSIGNIFICAN1 GEOMETAIC OTHE AEhlAAKS 4.2 4.6 4.2 K-2 2

Tee-to-Pipe 7-PR-A Pipe Restraint 9

Pipe-to-Elbow UT 600 3/28 w

dev, I g 2 VT 900-4/10 900-1/22 600-3/28

w. dcv.

I Q2 VT 900-1/22 300146 300147 300148 0 LJO IV, 45 T,60 X

O'L,45'T, 60 45'5'rc

strikes, gouges, and pits.

Seo CNF I1003?9.

Indications rcmovcd by light buffing.

Rccxamination was performed l>y Fl'L personnel.

Limited examination upstream I'rom ll" to 3" due to tce configuration.

Cal. Std.

TP-3-160-.438-SS-2.

Limited examination downstream from 4-1/4u to ?-I/2" due to inner radius of elbow.

Cal. Std. TP-3-160-.438-SS-2.

TURKEY I'OINT PIANT UNIT 3 1976 INSERVICE EXl5ltHhTION SUIalARY OF NONDESTRUCTIVE EXQllHATIOHS 2" IIIAIIIEAD SIS lAMP "8" (Seo Appendix A, Figure A-37)

ASME ASIIE SEC. XI SEC. XI ITEhlNO ~MTGY.

EXAMINATION AREA ID' NT IF I GATION Swnl WELD AOCEOUAI EXAM.SUh'I NOJAEV.

SIIEET NO.

NO AECOADABLE INDICATIONS INSIGNIFICANl GEOMETAIC OTIIEA AEhlAAKS 4.8 4.6 4.8 7

Pipe-to-Valve 7-PR-GG Pipe Restraint 12 Elbow-to-Pipe 900-1/22 300116 200-1/22 VT 900-4/10 300053 900-1/22 300117 200-1/22 X

X 4.8 32 Pipe-to-Elbow Vf PT 900-1/22 300118 200-1/22 4,6 4.6 K-2 K-2 38-'PR-Tl Pipe Restraint 40-I R-S Pipe Restraint VT 900-4/10 300033 VT 900-4/10 300054 4.8 J I 43 Elbow-to-Pipe Vl'T 900-1/22 300119 200-1/22

TURKI!Y POINT PIJUIT UNIT 3 1976 INSLRVICII L'Xi5IIHAT10N SUhflARY OP HOHDIM'RUCTIVII IIXAI41HATIONS 2" lllAIHEAD SIS CROSSOVER Soc A icn0ix A Fi uro A-37 AShIE ASME SEC. XI SEC. XI ITEMNO CATGY.

EXAhllNATION AIIEAIDENTIFICATION EXAM.

hIETIIOD SwrIII

'ROCEDURI NO.IAEV.

'LVELD EXAM.SUM SHEET NO.

INDICATIOI4S NO IIECOBDABLE INSIGNIFICAN1 GEOhIETAIC OTIIEA REMAIIKS 4.8 4.6 4,6 J-i K-2 K-2 3

Pipe to-Bib'-l'R-I'ipo Rostraint 7-PR Pipe Rcstroint 900-1/22 200-1/22 900-4/10 900-4/10 300120 300041 300040 X

X

TIIRKL'Y POINT PLANT UNIT 3 1976 IHSERVICE EXANItIATION SIINIARY OF NONDESTRUCTIVE EXANltIATIOHS 14" RIIR MOP "C" See A) endix A Fi urc A-38)

ASME SEC. XI ITEMNO AShIE SEC. XI CATGY.

E'XAhII NATION AREA IDENTIFICATION EXAM.

METHOD SwAI AOCEDUA NO.IAEV.

WELD EXAII.SUM SHEET NO.

INDICATIONS NO AECOADAOLE INSIGNIFICAN1 GEOhIETAIC OTHER AEMAAKS 4.2 J-I 6

Pipe-to-Valve 900-1/22 600-3/28

w. dov.

1 8 2 300149 X

O',O'I$,45',

45'Ti60'o exanination dounstream duo to valvo configuration.

Cal. Std. TP-14-140-1.250-SS-ll.

O~

TURKI>Y POINT I'LANT UNIT 3 IDT6 INSERVICE EXANINATION Sue)ARY OF NONI)ESTRIICTIVE EXANINATIONS 3" CIIARGING LINLI I.OOP "A" (Sec Ap endix A, I'igurc A-39)

AShlE SEC. XI ITEhlNQ AShlE SEC. XI CATGY.

EXAMINATION AREAIDENTIFICATION EXAM.

METIIOD SwRI ROCEDURI NO./REV.

IVELD EXAhl.SUM SIIEET NO.

INDICATIONS NO RECORDABlE INSIGNIFICAN GEOMETRIC OTHER REMARKS 4.2 6

)Ill>ow-to-Pipe 900-1/22 600-3/28 w

dave

~

I f> 2 300150 1.,45 f 45 60 Gouge and weld spatter.

Scc CNF I)100381.

Indications removed by light filing.

Rccxamination was performed by FPI.

pcrsonncl.

Limited examination upstream From 4-1/4" to 7-1/2" due to inner r:>dius of elbow.

One 60 indication duc to root geometry.

Scc Indication Resolution Record I310003.

Cal. Std. TP-3-160-.438-SS-2.

4.2 11 I'ipe-to-Elbow 900-1/22 600-3/28

w. dcv.

I f> 2 300121 X

0 L,45'T, 60 45 45 Onc 45'ndication d>>e to crown geometry.

Scc Indication Resolution Record l310004.

Cal. Std. TP-3-160-.438-SS-2.

4.2 K-2 24 Elbow-to-Pipe 25-PR-X Pipe Restraint 900-1/22 600-3/28

w. dcv..

I fj 2.

900-4/10 300122 300123 X

O'L,45'T,60'5 Cal. Std. TP-3-160-.438-SS-2.

Ilissing clamp bolt.

Scale reading:

5/8". -Sce CNF SI00360.

Bolt was replaced and scale reading was acccptcd "as is" by FPI, pcrsonncl.

TURKEY POINT PLANT UNIT 3 1976 IHSERVICE EXAMINATIONSU IIIARY Ol'ONDESTRUCTIVE EXANIHATIOHS 3" CIIARCIHC I.INE LOOP "C" (See Appendix A, Figuro A-40)

ASI.IE ASME SEC. XI SEC. XI ITEMNO CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOO SwAI WELO AOCEOUA EXAM.SUM NOSEY.

SHEET NO.

NO AECOAOAOLE INDICATIONS INSIGNIFICAN1 GEOMETAIC OTHER REMARKS 4.2 4.2 4.2 4.2 K-2 2

Elbow-to-Pipe 7-PR-IIN Pipe Restraint 18 Tce-to-Pipe 1

28 Elbow-to-Pipe 33 Tcc-to-Elbow 900-1/22 300124 600-3/28

w. dev.

IF>2 900-4/10 300088 900-1/22 300151 600-3/28

w. dev.

IF>2 900-1/22 300125 600-3/28

w. dev.

IF>2 900-1/22 300126 600-3/28

w. dev.

I f> 2 X

O'L>45'T O'L,O'W, 45'T X

O'L,45'5 T,60 X

O'L,45'5 T

454 604 45, 60 60'.imitcd examination upstream from 4-1/4" to 7-1/2" due to inner radius of elbow.

One 60 indica'tion due 'to inside surface geometry.

Scc Indication Resolution Record s310005.

Cal. Std. TP-3-160-.438-SS-2.

Shallo~ gouges <<ith sharp cdgcs.

Sce CNF I100374.

Indications removed by grinding.

Reexamination was porformcd hy FPL personnel.

Four 45'ndications duc to root geometry.

Onc 60'ndication due to root geometry and two GO'ndications duo to inside surface geometry.

Scc Indication Resolution Records 4310002 and I310008.

al. Std. TP-3-160-.438-SS-2.

Limited examination upstream from I-I/8" to 7-1(2" due to inner radius of elbow.

nil Std. TP-3-160-.438-SS-2.

ne 60 indication due to root geometry.

Scc Indication Resolution Accord t31000I.

al. Std. TP-3-160-.438-SS-2.

TURKI!Y I'Oll~lhtfl'NIT3 1976 INSRRVICB IlXANINA'I'IONSU)I>IARY Ol> tIONDILSTRUCTIVF> I!XAIIINATIONS 3" ('.IIAR(iltLG I.INI! 'I'I) VALVf: 312C (Sce A pcndix A, I>igurc A-4I)

ASI4C AShIE SEC. XI SEC. XI ITEh!tlO CATGY.

EXALUtIATION ABEA I DENT I F I CATIOtt SwBI WELD

'AOC E Ahb tIO./REV.

SIIEET NO.

INDICATIONS NO IIECOADADLE INSIGNIFICAttl GEOLIETll!C OTIIEI>

DEhIAAKS 4.6 '-2 K-2 44-PR-N Pipe Restraint SO-I'R-.l Pipe Restraint Vr 900-4/10 300127 Vf 900-4/10 300128 Restraint broken.

Scc CHF I10036il.

Restraint repaired and lu>sc plate added by Fl'I. pcrsonncl.

Drokcn U bolt.

Scc CNF lI00359.

U bolt rcplaccd and tightc<<cd by FPI. personnel.

4.6 K-2 50-PR-G Pipe Restraint VT 900-4/10 300129 U bolt loose.

Sec CHF I II)0367.

U bolt tightened by I>PL person<<cl.

1.6.

K-2 4.2 4.2 52-Plt-A2 Pipe Restraint 54 Pipe-to-Rlbou 56i Valve to P>pc VT

)00-4/10 300130 VT

)00-1/22 300152 100-3/28 dcv.

I fi 2 00-1/22 300153 00-3/28 deva I

f> 2 O'L,45'T 0

I.,O',45'5'T,60 45',60' bolt bent and loose.

Scc CHF II00366.

U bolt replaced and tightened l>y FPL pcrsonnol.

Iield spatter and nrc strikes.

Scc CHF 4100375.

Indications removed by light polish-ing.

Roexamlnation was performed l>y Fl'L pcrsonncl.

Limited examination upstream from I" to 4" due to branch connection.

Cal. Std. TP-3-160-.438-SS-2.

Held spatter.

Sco CIU> 1IOD376.

Indications removed by I igh t fi I-ing. 'eexamination was performed l>y FPI, personnel.

tto examination upstream d<<e tn valve configuration.

I.imitcd cx-aminatioi> downstream from 4-1/2" to 7-1/2" duc to inner railius of elbow.

Cal. Std. Tl'-3-160-.438-SS-2.

TIIRIiBY POItff PLAtff UNIT 3 191& IllSBRV ICE BXANINATIOIISCIhIARY OF IIOIIDFSTRIICflVBBXQIINATIOtlS I

A I

2" IJTDNIII I.ItlB IAXIP "B" (Soo A

ondIX A, Fignro A-42)

ASME AShlE SEC. XI SEC. XI ITEhINO CATGY.

EXAMINATIOtl AREA IDENTIFICATION SwR I WELD

'ROCEDUR EXAh'I.SUM NOIRE.

SHEET NO.

NO RECORDABLE ItIDICATIONS ItISIGNIFICAN GEOMETRIC OTIIER REhlARKS 4.6 f-2 11-PR Pipo Rostraint Vf DOa-4/IO 3OOODS

<0 TURKEY POIH'f FIANT UNIT 3 197G IHSERVICI'. EXAWIHATIOH SUIR4LRY OF HOHDFSTRUCTIVI'. I!XAHIHATIOHS 2" I.IIIDOIfH I.IHE 'l9 3 ORIFICES (Scc Appendix A, Figure A-43)

ASME ASME SEC. XI SEC. XI ITEMN

<MTGY.

EXAMINATION AREAIDENTIFICATION SwAI No IREV lVELD EXAM.SUhl SIIEE'T NO.

INDICATIONS NO RECORDABLE INSIGNIFICANl GEOh'IETRIC OTIIE0 nghlARKS 4.&

4.G K-2 6

Elbow-to-Pipo 6-PR Pipe Restraint 900-1/22 200-1/22 Vf 900-4/10 300132 300131 X

X U bolt missing and bracket bent.

Sco CNFl1003S& ~

U bolt replaced and bracket straightened by FI'I. personnel.

4.G K-2, 6-PR-A Pipe Restraint Vf 900-4/10 300070 4.&

12'ibow-to-Pip VT I'

900-1/22 200-1/22 300047 4.6 K-2 12-PR-0 Pipe Restraint VT 900-4/10 300071 4.&

22 Tcc-to-Pipe Vf PT 9ao-1/22 200-1/22 3aoo46 X

X 4.6 f.-2 24-PR Pipe Restraint VT 900-4/ IQ 300072 27 Pipe-to-Elbow VT PT 900-1/22 200-1/22 300073

TURKEY POINT PLAIIT UHIT 3

~ 1976 INSFRVICE EKAIIIHATIOHSIBIIIARY OF NONDESTRUCTIVE EXANINATIOHS I

2" SEAL IHJECTION LOOP "A" (Sco Appendix A, Figure A-44)

AShIE ASME SEC. XI SEC. XI ITEMN CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

~

hIETHOD, SwRI ROCEOUR NO./REV.

WELD EXAM.SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN'I GEOhIETRIC OTHER REhIARKS 4.8 4.6 K-2 6

Pipe-to-Elbow 8-PR-0 Pipe Restraint 900-1/22 200-1/22 900-4/10 300074 300158

!kissing support braco bolt.

See QIF II00337.

Bolt was replaced by FPL personnel.

4.6 4.&

4.6 4.8 4.6 4.6 K-2 K-2 14-PR-D Pipe Restraint 16 Pipe-to-Elbow 20-PR-1 Pipo Restraint 23 Elbow-to-Pipe 24-PR Pipe Restraint 24-PR-1 Pipe Restraint Vf PT 900-4/10 900-1/22 200-1/22 900-4/10 900-1/22 200-1/22 900-4/10 900-4/10 300043 300075 Seo cmarks 300002 300044 300045 300076 Sharp gougo.

Seo CNF I100347, Indication was removed after grind-ing.

Reexamination was performed by FPL personnel.

PT was not performed due to sharp gouge and will bo rcschedulod for an upcoming outage.

U bolt loose.

Scc QIF ll00339.

U bolt replaced and tightened by FPL personnel.

4.8 J>>l 36 Pipo-to-Elbow VT PT 900-1/22 200-1/22 300077

~~

TURKEY POIHT PLANI'NIT 3 197G IHSERVICE EXAillNATION,SUIQIARY Op HOHDESTRUCfIVE I!XAhllHATIOHS o II e

I x

I nre A-45 AShIE SEC. XI ITEMNO ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXAhl.

hIETIIOD Swnl

'AOCEDUAI NO.IAEV.

VjtELO EXAM.SUM Sl IE ET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN1 GEOhIETAIC OTIIER AEMAIIKS 4.G 4.G 4.8 4.8 4.6 4.6 K-2 K-2 K-2 K-2 i3-PR-n Pipo Rostraint 13-PR Pipe Restraint 18 Elbow-to-Pipe 28 Pipe-to-Elbow 28-PR-1 Pipe Restraint 28-PR-2 Pipe Rostraint VT PT 900-4/10 900-4/10 900-1/22 200-1/22 900-1/22 200-1/22 900-4/10 900-4/10 300079 300078 300080 300081 300082 300133 llanger loose.

Sec CHP I1003G4.

llangcr tigbtoned by FPI. porsonncl.

TURKFY POINT PLANT UttlT 3 1976 INSERVICL'XI&llNATIONSUNIARY OF tIONI)ESTRIICTIVE EXANltIATIONS 2" SEAI. INJECTION LOOP "C" Sce A

endfx A Fi uro A-46 ASME SEC. XI ITEMtt ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI ROCEDUR NO.IREV.

WELD EXAhI.SUhI SHEET NO.

ItIDICATIONS NO RECORDABLE INSIGNIFICAN1 GEOMETRIC OTHE REMARKS 4.8 4.6 4.8 4.6 J-1 K-2 J-1

'-2 19 Elbow-to-Pipe 26-PR-C Pipe Restraint 29 Valve-to-Pipe 32-PR-E Pipe Restraint VT PT VT PT 900-1/22 200-1/22 900-4/10 900-1/22 200-1/22 900-4/10 300083 300055 300084 300034

ATTACHMENT B 1976 INSERVICE EXAMINATION OF CLASS I COMPONENTS AT TURKEY POINO PLANTg UNIT NO

'4 FINAL REPORT Abstract:

Manual ultrasonic, manual liquid penetrant, fluorescent magnetic

particle, and visual techniques were used in the performance of the ISI examinations.

Twelve examination areas were found to have reportable visual indications.

Also, two of these areas revealed reportable liquid penetrant indications; one of these areas revealed reportable fluorescent magnetic particle indications; and one of these same areas revealed reportable ultrasonic reflectors.

These indications were reported to FPL on Customer Notification Forms (CNF's).

After disposition, one of the areas was reexamined by Southwest Research Institute (SwRI) personnel.

The results of this reexamination revealed that no recordable indications remained.

The remaining indications have been dis-positioned by FPL, and the areas have been reexamined and found acceptable by FPL personnel.

No other reportable indications were observed.

A more detailed discussion of the examinations performed, includ-ing Examination Summary Tables, is outlined in this attachment.

Further documentation of the examinations is available for inspection at the Turkey Point Plant.

TABLE OF CONTENTS Mi'IT 4 - FINAL REPORT LIST OF FIGURES LIST OF ABBREVIATIONS I.

INTRODUCTION A.

Examination Areas B.

Summary of Examination Results II.

NONDESTRUCTIVE EXAMINATION

SUMMARY

TABLE

~Pa e

~

~

1

~

~

11 l

~

~

2

~

~

4 A.

B.

C.

D.

E.

Examination Area Identification Examination Method Column Indications Columns Remarks Column Table Column

~

~

~

~

~

~

~

~

~

~

~

~

~

4 4

6 8

8 III ~

DISCUSS ION o

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

A.

Equipment B.

Examination Details 23 23 23

LIST OF FIGURES

~Fi ure

~Pa e

Root and Crown Indication Beam Paths 7

2 Beam Paths Used to Examine the Reactor Pressure Vessel-to-Flange t'feld.

24 Beam Paths Used to Examine the Closure Head-t'o-Fl ange Neld................,

24 Conceptual Drawings Showing Examination of RPV Closure Head Nut and Closure Head Stud........

25 Reactor Pressure Vessel Flange Ligaments........

26

LIST OF ABBREVIATIONS ASME AEC CNF DAC Dia FPL IQZ IDin.

ISI Lo MT NDT NRC OD PL PR PS PT RCC RGX RHR RL RPV RTD SIS SwRI UT VT American Society, of Mechanical Atomic Energy Commission Customer Notification Form Distance Amplitude Correction Diameter Florida Power 5 Light Company Heat-Affected Zone Inside Diameter inch, inches Inservice Examination Zero Reference Location Magnetic Particle Examination Nondestructive Examination Nuclear Regulatory Commission Outside Diameter Pipe Lug Pipe Restraint Pipe Support Liquid Penetrant Examination Reactor Coolant System Regenerative Heat Exchanger Residual Heat Removal Refracted Longitudinal Reactor Pressure Vessel Remote Thermal Detector Safety Injection System Southwest Research Institute Ultrasonic Examination Visual Examination Engineers

V' 2

~

~

I.

INTRODUCTION During the April-June 1976 refueling outage, Southwest Research Institute (SwRI) performed nondestructive examinations (NDT) of selected components in the Florida Power 6 Light Company's (FPL) Turkey Point Plant Unit 4.

These examinations constituted the second such Inservice Examination (ISI) performed at Turkey Point Plant Unit 4.

A.

Examination Areas The components examined were selected in accordance with the Florida Power 6 Light Company's (FPL) Turkey Point Plants Units 3 and 4 Technical Specifi-cations and with the 1970 Edition, including the Winter 1970 Addenda, of Section XI of the ASME Boiler and Pressure Vessel Code.

Representative samples of the components and/or areas in the following list were examined with nondestructive testing techniques:

Reactor Pressure Vessel and Closure Head Vessel-to-Flange and Closure Head-to-Flange Welds Closure Studs,

Nuts, and Washers Ligament Areas of the Vessel Flange Closure Head Cladding Pressurizer Upper Shell Course-to-Upper Head Weld Nozzle Inside Radius Sections Surge Nozzle and Safety Nozzle A

Heater Connections Bottom Head-to-Support Skirt Weld Steam Generator A

Primary Inlet and Outlet Nozzle Inside Radius Sections Re enerative Heat Exchanger Support Lug Weld and Clamp Restraint

~Pi in humain Reactor Coolant System 2-in. Remote Thermal Detector--Loops "A" (Hot Leg) and "B" (Cold Leg)

4-in. Pressurizer Spray--Loops "B" and "C" 3-in.

and 4-in. Pressurizer Relief 2-in. Boron Injection--Loops "B" and "C" 2-in. High Head Safety Injection System--Loop "B" and Crossover 3-in. Charging LineLoops "A" and "C" and to Valve 312C 2-in. Letdown Line--Loop "B" and to Three Orifices 2-in. Seal Injection--Loops "A" and "B" Reactor Coolant Pum s Pump A--Seal Housing Bolting, Pump Support No.

1, and Pump Support Structures Nos. 1, 2, and 3

Pumps A, B, and C--Flywheels B.

Summary of Examination Results The examinations were performed in accordance with the 1968 Edition of Section III, Appendix IX, of the ASME Boiler and Pressure Vessel Code, the FPL's Turkey Point Plants Units 3 and 4 Technical Specifications, and the Nuclear Regulatory Commission's (formerly Atomic Energy Commission)

Regula-tory Guide 1.65. The nondestructive examinations were performed using manual ultrasonic, manual liquid penetrant, fluorescent magnetic particle, and visual techniques.

The various examinations were conducted in accordance with standard SwRI NDT procedures which were written to conform to the require-ments of the applicable sections of the ASME Boiler and Pressure Vessel Code and the SwRI Nuclear Quality Assurance Program Manual.

A copy of each appli-cable SwRI procedure is included in Appendix D.

Reportable visual indications were observed on twelve examination areas.

These indications were reported to FPL personnel on Customer Notification Forms (CNFs) for disposition.

One of these indications was removed by FPL personnel, and the area was reexamined by SwRI personnel.

No recordable indications were observed during the reexamination.

Eight other indications were dispositioned and the areas were reexamined and found acceptable by FPL personnel.

Two other areas, weld No.

RCC-(B) -5 and spare nut No. 122, were accepted "as is" by FPL, and one remaining indication on spare stud No. 45 will be corrected by FPL when available plant machine shop time permits the machining of the stud.

Two reportable liquid penetrant indications were observed; one on weld No. RCC-(A) -5 and one on nut No. S-l.

These indications were reported to FPL personnel on CNFs for disposition.

The indication on weld No.

RCC-(A) -5 was

removed, and the area was reexamined by SwRI personnel.

No recordable indi-cations were observed during the reexamination.

FPL personnel replaced nut No. S-l with a spare and, thus, the CNF was closed.

One reportable fluorescent magnetic particle indication on spare stud No. 45 was reported to FPL.

The stud was shipped to the manufacturer's plant for evaluation.

The ultrasonic examinations revealed one reportable and several insignif-icant indications.

The reportable indication on nut No. S-l was reported to FPI. on a CNF.

With the replacement of nut No. S-l by a spare, the CNF was closed.

Test data (instrument calibration data and examination results) for examinations are recorded on standardized SwRI forms.

A copy of each of the instrument calibration sheets and examination data sheets completed onsite is included in Volume III.

Test personnel were certified in accordance with established SwRI per-sonnel certification procedures and with "SNT-TC-1A," American Society for Nondestructive Testing.

For clarification and ASliE Code compliance purposes, it should be emphasized that the SwRI test personnel performed "examinations".

and were not acting as "inspectors."

As defined in Paragraphs IS-202, IS-203, and IS-223 of Section XI of the Code, an "inspector" is an employee of an insurance company or a State or a municipality who, among other responsi-bilities, also has the duty to verify the owner's or his agent's certification of an operation in accordance with SNT-TC-lA.

He also has the duty of auditing the examination program and requiring requalification of an operator when the inspector has reason to question the performance of that operator.

The SwRI Quality Assurance and Reliability Engineering Section was represented onsite by the SwRI quality assurance (QA) representative, who was present for the majority of the examination period.

The QA representative performed all appropriate duties as outlined in Section 5.2.1.4, "Onsite SwRI Quality Assurance Activities," of the "Project Plan for the 1976 Inservice Examination of Turkey Point Plant, Unit 4".

I I.

NONDESTRUCTIVE EXAMINATION

SUMMARY

TABLE The Nondestructive Examination Summary Table (Page

9) provides the results of the nondestructive examinations performed to satisfy the ASME Section XI, FPL's Turkey Point Plants Units 3 and 4 Technical Specifica-

tions, and NRC (formerly AEC) Regulatory Guide 1.65 requirements.

The table lists the examination areas,

methods, and results.

It is divided into sections according to major systems or components and then subdivided to list the actual component,

area, or weld examined.

Several columns are self-explanatory, but the following comments may be helpful in interpreting the data as presented.

A.

Examination Area Identification Column In the column "Examination Area Identification," the weld identification system used by SwRI is the same as that used by Westinghouse during previous examinations, with a few exceptions.

The exceptions are as follows:

(1)

Branch connections are numbered as part of the main run of piping as opposed to being numbered as the first weld on the branch line.

In general, the branch connections are numbered by adding "BC" to the weld identification of the circumferential weld numerically preceding the branch connection.

When more than one branch connec-tion is located between two circumferential welds, an additional digit (-1, -2, etc.) is added for uniqueness.

(2)

In general, piping attachments are numbered by adding a "PL" for piping lug, a "PR" for nonwelded piping restraint, or a "PS" for welded piping support to the circumferential weld numerically're-ceding the component.

In addition, for pipe supports and restraints previously identified, the Westinghouse letter designation follows the above-described identification.

When more than one piping attachment is located between two circumferential welds, an addi-tional digit (-1, -2, etc.) is added when necessary to establish uniqueness.

For example, "2PL-A-2" is the piping lug following circumferential weld No. 2, previously designated as "A" by West-inghouse; and it is the second lug numbered.

B.

Examination Method Column 1.

Visual (VT)

Areas requiring VT were classified as follows:

Piping restraints were examined in accordance with SwRI Proce-dure NDT-900-4, Revision 10.

This procedure includes the guide-lines outlined in Section XI and specifies methods of documenting indications.

The remaining nuclear power plant components requiring VT were examined in accordance with SwRI Procedure NDT-900-1, Revision 22.

This procedure includes the guidelines outlined in Section XI and specifies methods of documenting indications.

2.

Li uid Penetrant (PT) t Manual PT examinations were performed in accordance with SwRI Procedure NDT-200-1, Revision 22, using a visible red-dye penetrant.

Liquid penetrant material certification sheets are included in Appendix F.

3.

Magnetic Particle (nfl')

Fluorescent MT examinations were performed in accordance with SwRI Procedure NDT-300-2, Revision ll.

Magnetic particle material certification sheets are included in Appendix F.

4.

Ultrasonic (UT)

The specific manual UT procedures employed in any particular examina-tion covered by this report are detailed in'ppendix D.

Welds and areas were subjected to examination scans discussed in the following subsections.

Exceptions to these tests were usually due to area/component configurations and/or inaccessibility.

a.

Lamination Scan (O'L).

A 0-deg longitudinal wave was used to examine the base metal adjacent to the welds, to determine the existence of any laminations or inclusions which, if present, would cast "shadows" which could prevent sound beam access to all or part of the welds and/or could offset the interpretation of weld examination results

[see Paragraph IX-344(c) of Appen-dix IX to Section Ill].

(g b.

Lon itudinal Wave Weld Scan (O').

In cases where the physical configuration prohibits shear wave examinations from one of the two sides of the" weld, a 0-deg longitudinal wave examination was performed from the surface of the weld.

These examinations are consistent with the requirements of Paragraph IX-342 of Appendix IX to Section III and are used to determine the existence of any reflectors in the weld positioned parallel to the surface of the weld.

c.

Strai ht Beam Scan (0').

In the case of the'PV Closure Head Nuts, and RPV Ligaments, a 0-deg straight beam examination was performed to determine the existence of any reflectors propagating from the root of the threaded areas to the base material, positioned parallel to the surface of the examination area.

d.

Refracted Longitudinal Wave Scans (RL).

For the coverage of certain welds and areas, refracted longitudinal wave search units were used to perform the examination scans.

The refracted angle is included in the Non-destructive Fxamination Summary Table along with the "RL" designation.

e, Shear Wave Scans (45', 45'T, 60').

Each weld was examined using 45-and 60- eg shear waves to determine the internal characteristics of the weld metal

and, when required, the adjacent base metal for one thickness beyond the edge of the weld.

Examinations were performed from both sides of the weld, whenever possible, using the required test angles.

In addition, a transverse scan (applied along the weld to detect any reflectors oriented "transverse to the weld") using a 45-deg shear wave search unit was also performed, whenever possible, C.

Indications Columns The four columns under the general heading of "Indications" are "No Record-able," "Insignificant," "Geometric,"

and "Other."

The results for the VT, manual PT, and fluorescent MT examinations are indicated by an -"X" in the appropriate column to be either "No Recordable,"

"Insignificant," or "Other."

Vl'xaminations were performed in accordance with the guidelines of Paragraph IS-211 of Section XI.

For visual indications, the term "Insignificant" was applied when minor surface irregularities were observed.

The term "Other" was used to describe the indications which were deemed reportable to FPL'ersonnel for evaluation and/or disposition.

Manual PT and fluorescent MF examinations were performed and the results were evaluated in accordance with the requirements of Articles 3 and 6 of Section III of the ASME Boiler and Pressure Vessel Code.

For these examinations, the term "Insignificant" was applied when indications which did not exceed the acceptance standards were observed.

The term "Other" was used to describe indications which were deemed reportable to FPL personnel for evaluation and/or disposition.

The results for the manual UT examinations are indicated by recording the angle of the ultrasonic search unit (see paragraph II.B.4 above) under the column heading which describes the test results for that angle, i.e., the "No Recordable," "Insignificant," "Geometric," or "Other" column.

In the per-formance of the UT examinations, the data recording level was established by the applicable nondestructive testing procedure.

Generally, the recording level for manual ultrasonic examinations of piping is 50 percent of the Distance Amplitude Correction (DAC) Curve established during instrument calibration, and the recording level for manual UT examinations of pressure vessels is 20 per-cent of the DAC when the configuration and acoustic properties of the vessel or area permit.

Specifically, The term "No Recordable" was applied when no indications were observed or when the amplitudes of the indications were below the recording level that the particular SwRI NDT operating pro-cedure specifies.

"Insignificant" was applied when the amplitude of any indication was equal to or greater than the recording level that the particular SwRI NDT operating procedure specifies but less than 100 percent of DAC.

"Geometric" indications are those indications which have an ampli-tude equal to or greater than 100 percent of the DAC and are generally resolved as due either to "root" geometry, "crown" geo-metry, "inside surface" geometry, or "outside surface" geometry.

An indication due to "root" geometry is one in which the ultra-sonic wave is reflected by the root geometry of the weld bead; "crown" geometric indications occur when the ultrasonic wave reflects off the inside surface of the examination area, strikes the crown of the weld, and is returned to the transducer; "inside surface" geometric indications occur when the internal surface of the examination area or the weld fitup contains an angular plane sufficient to reflect a portion of the ultrasonic beam back to the transducer; and "outside surface" geometric indications occur when the ultrasonic wave reflects off the inside surface of the examina-tion area, strikes the roughness of the outside surface of the examination

area, and is returned to the transducer.

Figure 1

illustrates typical "crown" and "root" indication paths.

TRANSDUCER TRANSDUCER ROOT PATH CROWN PATH FIGURE 1.

ROOT AND CROlfN INDICATION BEAM PATHS The "Other" indications include those which have had an amplitude equal to or greater than 100 percent of the DAC and were not included in the column of "Geometric" indications, as described above.

Also, if any indications existed that were determined to be caused by rejectable conditions such as cracks, lack of fusion, etc., they were included in this column.

D.

Remarks Column The "Remarks" column is used to provide additional information pertinent to the examination results:

When complete coverage of the examination area was not possible, the "Remarks" column was used to indicate the limitations.

For VT, manual PT or fluorescent examination results reported in the "Other" column, a brief description is, given in the "Remarks" column.

For ultrasonic examination results reported in the "Other" column, a brief description of the resolution of the indications is pre-sented in the "Remarks" column.

Reference is made in the "Remarks" column to CNFs used in the reporting of indications.

E.

Table

{See Pages 9 through 22)

TURKEY POIVf PLANT UNIT 4 1976 INSERVICE NOHDESTRUCfIVE IIXAHINATIOHSUMIARY TABLE REACTOR PRESSURE VESSEL AND CLOSURE llEAD (See Ap endix A, Figure A-I)

ASME SEC. XI ITEMN ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI ROCEDUR NO./RE V.

'LVELD EXAM$. SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER REMARKS IIeid A Vessel-to-Flange 00-13/14 300066 6.5 RL 1.5 RL 11.5 RL 33-1/3'f weld length was examined from the seal surface (from the cen-terline of stud hole No. I to the centerline of stud holo No. 19).

1.3 1.8 G-l Closure llead-to-Flange Closure IIead Studs Uf 00-15/21 00-1/22 300080 300072 OK$45T$ 45

$ 0 L 60 33-I/3~i of weld length was examined from the closure head dome side (from the centerline of stud hole No. l to the centerline of stud hole Ho. 19).

No examination from 0" to 2" in L and 6-5/8" to 14" in N, and no examination from 2" to 4-1/2" in L and 0" to 6 5/8" in h due to refer-ence arrow.

No examination from 75" to 81" due to lifting lug.

Studs Hos.

6 through 23 and spare stud No.

45 were examined.

Flattened thread on spare stud Ho. 45.

See CNF 100331.

00-2/11 00-18/13 60 Examination performed to eeet Regulatory Guide 1.65 requirements.

Flattened thread on spare stud No. 45.

See CHF 100331 (same as visual indication).

TURKEY POINT PLANT UNIT 4 1976 INSERVICE NONDESTRUCTIVE EXAMINATION SIÃMARY TABLE REACTOR PRESSURE VESSEL AND CLOSURE HEAD (See Appendix A, Figure A-1)

(Cont'd)

ASME ASLIE SEC. XI SEC. XI ITEMN CATGY.

E XAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI WELD ROCEDUR EXAM.SUM NO.IREV.

SHEET NO.

NO RECORDABLE INDIGATI0 NS INSIGNIFICAN GEOMETRIC OTHER REMARKS 1.8 G-l Closure llead Nuts VT 900-1/22 300079 PT 200-1/22 00-19/13 0,45 00 huts Nos.

6 through 13, S-l, 15 through 31, 33 through 42, and spare nuts Hos.

121 and 122 were examined.

Nuts Nos.

24 through 31 and 33 through 42 received a visual exami-nation only.

Visual indications on nuts Nos. S-l (drilled holes),

18 (dented threads),

121 (rust on the outside surface),

and 122 (scratches on the outside surface).

See CNFs 100329,

100330, and 100332.

FPI. closed the CXFs by doing the following: (I) Replaced nut No. S-l with spare nut No.

122, (2) Dressed the threads on nut No. 18, (3) Cleaned and applied preservative coating on nut No.

121, (4) Accepted nut No.

122 "as is".

Examinations performed to meet Regulatory Guide 1.65 requirements.

Surface indications on nut No. S-l (same as visual indications).

See CNF 100330.

Nut Ho. S-l was replaced by spare nut No.

122.

Ultrasonic indications on nut No. S-I (same as visual and liquid penetrant indications).

See CHF 100330.

Nut No. S-l was replaced by spare nut.

No.

122.

1.9 1.10 G-I G-l Ligaments Between Threaded Stud Iloles Large Closure Washers 00-5/15 300067 VT 900-1/22 300075 00 18 ligament areas were examined (from the centerline of stud hole No. I to the centerline of stud hole No. 19).

Washers Hos.

6 through 23 and spare washer No.

118 were examined.

PT 200-1/22 Examination performed to meet Regulatory Guide 1.65 requirements.

~-

TURKEY POIiiT I'lAiT UNIT 4 1976 INSERVICE NOiNDESTRUCTIVE EXAtIINATIONSUGARY TABLE REACTOR PRESSURE VESSEL AND CLOSURE HEAO (See Appendix A, Figure A-I)

(Cont'd)

ASME SEC. XI ITEMN ASME SEC. XI CATOY.

EXAMINATION AREA IOENTIFICATION EXAM.

METHOD Svrnl ROCEOUR NO.IREV.

MELO EXAM.SUAI SHEET NO.

INDICATIONS NO RECOROABI.E INSIGNIFICAN GEOMETRIC OTHER REMARKS 1.10 G-I Small Closure Ilashers Vl'00-1/22 300077 Nashers Nos.

6 through 23 and spare washer No.

118 were examined.

1.13 I-1 Closure Head Cladding PT 200-1/22 900-1/22 200-1/22 300081 Examination performed to meet Regulatory Guide 1.65 requirements.

Two 6" x 6" patches were examined.

Lo location for patch No. I is the centerline of stud hole No. I and for patch No.

2 is thc centerline of stud hole No.

S.

No location for both patches is 8" from the flange lip to the bottom of.thc patch.

TURKEY POINT PLANF UNIT 4 1976 INSERV ICE NONDESTRUCTIVE EXAMINATIONSIMIARY TABLE PRESSURIZER (See Appendix A, Figures A-2 and A-3)

AS'VIE SEC. XI ITEMNO ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXALI.

METHOD SwRI ROCEOUR NO.IREV.

WELD EXAM.SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER REMARKS 2.1 POI-3 Upper Shell Course-to-Upper Head 900-1/22 600-15/21 300049 X

L,O N,45 T, 54,604 IS" of weld length were examined (from 50" to 65")

2.2 Safety Nettle A

Inside Radius Section 600-28/5 300039 4 RL 2.2 Surge Nettle Inside Radius Section 00-28/5 300005 4 RL 2.4 2.6 2.7 E-2 G-2 Heater Connections Nos.

1 through 78 Pressure-Retaining Bolting Nanway Closure Vessel Support Bottom Head-to-Skirt 00-1/22 00-1/22 900-1/22 600-15/21 300041 300040 300048 X

L,45 T O'1,45

,60 Examination performed to comply with Tcchnical Specifications commitments.

Heater B2 Insulation boot burned through.

Heater 86 Insulation covering below wiring.

Heater 838 Insulation boot split.

Sce CNF 100326.

The remaining 75 heaters had no recordable indications.

FPL repaired the heaters with indi-

cations, closing CNF 100326.

The first five bolts counterclock-wise, starting at the top of the manway, were examined in place.

36" of weld length were examined (from 248" to 284").

No examination above the weld due to insulation ring obstructing area of interest.

TURKEY PO1%

PIANOS WilT 4 1976 INSERYICE NONOESTRUCTIYE EKQHNATION SECTARY TABLE STEAM GENERATOR A (See Appendix A, Figure A-4)

ASME SEC. XI ITEMN ASMC SEC. XI

~WTGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI ROCEOUR No.iREV.

WELD EXAM.SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN GEOhIETRIC OTHER REMARKS 3.2 Primary Inlet Nozzle Inside Radius Section 600-28/5 300083 39 RL Primary Outlet Nozzle Inside Radius Section 600-28/5 300082 39 RL No examination in the area of the support lug due to inaccessibility.

TURKEY POINT PLANT UNIT 4 1976 INSERVICE NONDESTRUCTIVE EXAMINATIONSIDINARY TABLE REGENERATIVE JIEAT EXCHANGER (See Appendix A, Figure A-S)

ASMC, ASME SEC. XI SEC. XI ITEhINO CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI WELD ROCEDUR EXAMl.SUhI NO./REV.

SHEET NO, NO RECORDABLE INDICATIONS INSIGNIFICAN GEOMETRIC OTHER REMARKS 1ÃIEGRALLY WELDED SUPPORT SllSLL I 3.6 RGX (I)-Lug CLAHP RESTRAINT 900-1/22 200-1/22 300032 UT examination not feasible.

SHELL I RGX (I)-CR VT 900-4/10 300033 Examination performed to comply with Technical Specifications commitments.

TURKEY POINf PLANf UNIT 4 1976 INSERVICE NO!iiDESTRUCfIVE EXAMINATIONSIBIIIARY TABLE PIPING ASh'IE ASME SEC. XI SEC. XI EXAMINATION ITEAIN CATGY AREA IDENTIFICATON SwRI EXAM.

ROCEDUR METHOD NO IREy WELD EXAM.SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHE REMARKS REACTOR COOLANI'OP "A" p

~Fi 0 A-6) 29" I.D.

4.1 RCC-(A)-4 L'lbow-to-Nozzle 31" I.D.

900-1/22 200-1/22 600-3/26 Dev.

IC2 300084 X

X 0 L,O'II,45 T, 45,60 No examination from the downstream side due to the nozzle configuration.

Examination limited to 3-1/4" in H from the upstream side due to the elbow configuration.

4.1 F

RCC- (A)-5 Nozzle-to-Flbow REACfOR COOLANT LOOP "B" See A

endix A Fi ure A-7 29u I 0 900-1/22 900-1/22 PT 200-1/22 PT 200-1/22 600-3/26 Oev. Ifi2 300085 0 L,O NJ45 T, 45,60 Drilled hole.

See CHF 100325.

No recordable indications after cosmetic grinding.

Drilled hole (same as visual indi-cation).

No recordable indications after cosmetic grinding.

No examination from the upstrean side due to the nozzle configuration.

Examination limited to 3-1/4" in à from the downstream side due to the elbow configuration.

4.1 4.1 RCC-(B)-4 Elbow-to-Nozzle 31'i I D

RCC- (B) -5 Nozzle-to-Elbow VT 900-1/22 900-1/22 300084 300085 Examination performed due to VT indi-cation on weld No. RCC-(A)-5, in order to comply with ASNE Section XI paragraph IS-244 requirements.

Examination performed due to VT indi-cation on weld Ho. RCC-(A)-5, in order to comply with ASNE Section XI paragraph IS-244 requirements.

Small gouges.

See CHF 100333.

Accepted "as is" by FPL.

TURKEY POIhT PLANT UNIT 4 1976 INSERVICE NONDESTRUCTIVE EXAMINATIONSIDMARY TABLE PIPING (Cont'd)

ASIJE SEC. XI ITEMN ASME SEC. XI CATGY.

E XAMINATION AREA IDENTIFICATION SwRI EXAIJ.

ROCEDUR METHOD NO /REy WELD EXAM.SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER REMARKS 4.6 K-2 2" RTD IIOT LEG LOOP "A" See A

endix A, Fi ure A-IS 7-PR-D Pipe Restraint VT 900-4/10 300020 K-2 2" RTD COlA) I.EG LOOP "B" (See A

endix A FiIIurc h-19) 15-PR-A-1 Pipe Restraint VT 900-4/10 300007 4" PRESSURIZER SPRAY LOOP "B" See A

cndix 4.6 4.6 4.6 K-2 K-2 K-2 9-PR-D2 Pipe Restraint 9-PR-El Pipe Restraint 14-PR-N Pipe Restraint VT 900-4/10 VT 900-4/10 VT 900-4/10 300008 300009 300021

TURKEY POINT PLANT UNIT 4 1976 INSERVICE NONDESTRUCTIVE EXAMINATIONSIBNARY TABLE PIPING (Cont'd)

ASME SEC. XI ITEMN ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI WELD ROCEOUR EXAM.SUM NO.IREV.

SHEET NO.

NO RECORDABLE INDICATIONS INSIGNIFICAN GEOMETRIC OTHER REMARKS 4.6 4.6 4.6 4.6 K-2 K-2 K-2 K-2 4" PRESSURIZER SPRAY LOOP "C" Sce A

endix A, Fi urc A-26 6-PS-B Pipe Support Structure 7B-PR-Ll Pipe Restraint 12-PR-L4 Pipe Restraint 13-PR-LS Pipe Restraint VT 900-4/10 300022 VT 900-4/10 300010 VT 900-4/10 300011 VT 900-4/10 300012 Scale reading 2-3/4".

Scale reading on mark No. 3.

4.6 3" AND 4" PRESSURIZER RELIEF (See A

endix A,

~Fi <<re A-22 8-PR-C Pipe Restraint VT 900-4/10 300030

PIPING (Cont'd)

TURKEY POINT PLANf UNIT 4 1976 INSERYICE NONOESTRUCfIVE EXAMINATION

SUMMARY

TABLE ASSIE "ASME SEC, XI SEC. XI ITEMN CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD Swnl

'LVELO ROCEOUR EXAM.SUM NO./REV.

SHEFT NO.

NO RECORDABLE INOICATIONS IN S IG NIF ICAN GEOMETRIC OTHER REMARKS 2"

LETDOWN LINE LOOP "B"

Sce A

endix A, Fi ure A-42 4.6 K-2 12-PR-B Pipe Restraint 900-4/10 300019 4.6 4.6 K-2 K-2 2" I.ETOOÃN LINL'O THREf: ORIFICES (See A

cndix A, Fi ure A-43) 16C-PR-E Pipe Restraint 18-PS-C Pipe Support Structure 900-4/10 300026 900-4/10 300027 2"

BORON INJECTIM LOOP "B" (See A

endix A Fi urc A-33 4.6 4.6 4.6 4.6 K-2 K-2 K-2 K-2 7-PR-C Pipe Restraint 9-PR-F Pipe Restraint 13-PR-L Pipe Restraint 15-PR-N Pipe Restraint 900-4/10 300013 900-4/10 300014 900-4/10 300015 900-4/10 300016 4.6 K-2 2" BORON ItuECfION LOOP "C" (See A

cndix A,

~Fi re A-54 11-PR-K Pipe Restraint 900-4/10 300017

PIPING (ContFd)

TURKEY POII<<FT PLAÃf IPiIIT 4 1976 INSERVICE NONDESTRUCTIVE EXAMINATIONSIDDIARY TABLE ASME ASME SEC. XI SEC. XI ITEMN CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI ROCEDUR NO.IREV.

AFIELD EXAM.SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER REMARKS 4.6 K-2 2" lllG)l llEAD SIS LOOP "B" AND CROSSOVER Sec A

endix A, Fi ures A-37 and A-37a) 10-PR-P Pipe Restraint 900-4/10 30001B 4.6 4.6 4.6 4.6 K-2 K-2 K-2 K-2 3" CIIARGING I.INE LOOP "A"

Scc A

endix A

~F<< A-FF)

B-l'R-B Pipe Restraint 10-PR-E Pipe Restraint 14-PR-K Pipe Restraint 20-PR-0 Pipe Restraint 900-4/10 900-4/10 900-4/10 900-4/1D 300054 300051 300052 300053 4.6 4.6 4.6 4.6 4.6 K-2 K-2 K-2 K-2 K-2 3" CIIARGING LINE LOOP "C"

See A

endix A

~F) <<rc A-CF) 13-PR-B Pipe Restraint 14-PR-E Pipe Restraint 23-PR-I Pipe Restraint 36-PR-Ll Pipe Restraint 37-PS-N Pipe Support Structure 900-4/10 900-4/10 900-4/10 900-4/10 900-4/10 30005B 300057 300056 300055 300023

'IURKEY POINT PLANT UNIT 4 1976 INSERVICE NONDESTRUCT1VE EXANINATIONSUIRY TABLE PIPING (Cont'd)

ASME ASME SEC. XI SEC. XI IT Ehl N CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI IVELO ROCEDUR EXAhI.SUM NO.IREV.

SHEET NO.

NO RECORDABLE INDI GATI0 NS INSIGNIFICAN GEOMETRIC OTHER REMARKS 3" CIIARGING LINE TO VALVE 312C (See A

en-dix A Fi ure A-411 4.6 4.6 4.6 4.6 4.6 4.6 4.6 4.6 K-2

'-2 K-2 K-2 K-2 K-2 K-2 K-2 K-2 K-2 7-PR-A Pipe Restraint 8'PR-0 Pipe Restraint 8-PR-F Pipe Restraint 8-PR-J Pipe Restraint 9-PR-L Pipe Restraint 15-PR-R Pipe Restraint 17-PR-T Pipe Restraint 21-PR-V Pipe Restraint 21A-PR-N Pipe Restraint 21A-PR-X Pipe Restraint VT 900-4/10 300059 VT 900-4/10 300060 VT 900-4/10 300061 VT 900-4/10 300062 VT 900-4/10 300024 VT 900-4/10 300025 VT 900-4/10 300044 VT 900-4/10 300045 VT 900-4/10 300046 VT 900-4/10 300038 "U" bolt missing from support.

See CNF 100328.

Repaired by FPL.

Restraint disconnected from the Mall.

Scc CNF 100327.

Repaired by FPL.

4.6 K-2 23-PR-Y Pipe Restraint VT 900-4/10 300047

PIPING (Cont'd)

TURKEY POINT PLILVT UNIT 4 1976 INSERVICE NONDESTRUCTIVE EXAIFIINATIOefS(BS4ARY TABLE AS4ME SEC. XI ITEMN ASME SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION EXAM.

METHOD SwRI ROCEOUR NOJREV.

WELD EXAM.SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER REMARKS 4.6 4.6 K-2 K-2 2" SEAL INJECTIOel LOOP "A" (See A

endix A,

~Fi <<re 4.44 14-PR-B Pipe Restraint 18-PR-B1 Pipe Restraint 900-4/10 900-4/10 300034 300035 4.6 K-2 K-2 2" SEAI. INJECTI(N LOOP "0" (Scc hi cndix A,

~ri re *-44) 31-PR-L Pipe Restraint 37-PR-0 Pipe Restraint 900-4/10 900-4/10 300036 300037

'IURKEY POINT I'LANT UNIT 4 1976 INSERVICE NONDESTRUCTIVE EXAMINATIONSU&IARY TABLE REACTOR COOLANT PUMPS (See Appendix A, Figures A-47 and A-48)

ASME SEC. XI ITEMNQ ASh'IE SEC. XI CATGY.

EXAMINATION AREA IDENTIFICATION E XAAI.

METHOD SwRI ROCEDUR NO./RE V.

WELD EXAM.SUM SHEET NO.

INDICATIONS NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER REMARKS 5.5 5.6 G-2 K-1 PUMP A Seal Housing Bolting 4 Studs and 8 Huts Pump Support sl VT PT UT 900-1/22 900-1/22 200-1/22 300042 300050 X

X The bolting was examined in place.

Ho examination from 38" to 63" due to support configuration.

Ho available technique for UT examination.

5.7 K-2 Pump Support Structure ll 900-4/10 300002 5.7 K-2 Pump Support Structure s2 900-4/10 300003 5.7 K-2 Pump Support Structure t3 Flywheel 900-4/10 600-6/11 300004 X

300043 O'L,45 Examination was performed in place at bore, keyways, and tapped holes.

PUMP B

Flywheel 600-6/11 300001 0 L>45 Examination was performed in place at bore, keyways, and tapped holes.

PUMP C Flywheel 600-6/11 300029 0 L,45 Examination was performed in place at bore,

keyways, and tapped holes.

~ ~

III.

DISCUSSION This section of the.report provides a description of the equipment used during the ISI and also provides the examination details of each component.

A.

~Eui ment l.

Ultrasonic a.

Flaw Detection Instruments.

Sonic FTS Mark I ultrasonic instruments were used for the manual ultrasonic (UT) examinations.

The Sonic FTS Mark I flaw detection instruments consist of small, lightweight, portable units, including rechargeable battery/charger packs.

These battery chargers provide a method of recharging the batteries in the tester, as well as provid-ing alternating current (AC) power directly to the instruments.

'Also, by nature of the battery charging system, theseinstruments maintain constant performance characteristics even though 110-volt service line voltage typically varies at a plant site.

The devices utilize transistorized circuits of printed circuit board construction and a cathode ray tube (CRT) for a video display of the test data.

They are capable of being used with either direct contact or immersion testing techniques and can be used for single-or dual-transducer testing.

A list of the Sonic FTS Mark I instruments used for these examina-tions along with their calibration certifications can be found in Appendix F.

b.

Transducers.

Various brands,

sizes, types, and frequencies of UT transducers (search units) were used to perform these examinations.

A list of the transducers used for the Turkey Point Plant Unit 4 ISI program, along with their calibration certifications can be found in Appendix F.

For information on the actual transducer used for any specific examination, consult the calibration and data sheets in the copies of the original data.

2.

Magnetic Particle YP black light was used for the detection of fluorescent magnetic particle indi-cations.

The intensity of the light was over 100 ft-candles at 15 inches distance from the bulb during calibration for certification.

b.

Yoke.

A Parker adjustable probe yoke was used to induce longitudinal magnetic fields on the components'xamined.

The yoke worked on ac.

As demonstrated during calibration for certification, with probe spacing of 8 inches, the yoke induced magnetic fields equivalent to the prod method of 8-inch spacing at 27.5 amperes/inch.

B.

Fxamination Details The data taken during the examinations were evaluated in accordance with the criteria in each nondestructive testing procedure.

For ultrasonic exami-nations of piping, the evaluation criteria (Paragraph 8.0 of SwRI Procedure NDT-600-3, Rev.

26) states that "Any indications producing a response greater than 20 percent of the reference level and suspected by the operator to be other than geometrical in nature shall be investigated by a Level II or Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector."

23

4 ~

In consonance with these criteria, the following was'recorded on the examination record sheets:

If there were no indications observed which were above 20 percent of DAC, "No Recordable Indications" was recorded.

If each indication observed was above 20 percent. of DAC and less than 50 percent of DAC, "All indications investigated as per Paragraph 8.0" VESSEL TO FLANGE EXAMINATION was recorded.

If some indications observed were between 20 and 50 percent of DAC while others were above 50 percent of DAC, both of the preceding state-ments were recorded.

1.

Reactor Pressure Vessel a.

Reactor Pressure Vessel-to-Flan e

Circumferential Weld.

The Reactor Pressure Vessel-to-Flange Circumferential Weld (Weld A) was examined ultrasonically from the flange seal surface.

A module containing three trans-

ducers, mounted such that 1.5-, 6.5-,

and 11.5-deg refracted longitudinal waves were introduced into the material, was manually

'applied to the seal surface as shown in Figure 2.

Three scans, one for each angle, were per-formed during the examination.

The angles and the scans were chosen to ensure total coverage of the weld.

Of the weld length, 33-1/3 per-cent was examined (from centerline of stud hole No.

1 to centerline of stud hole No.

19) in accordance with the requirements of the ASME Section XI.

Calibration standard No.'-CSCL-1-TKY was used to calibrate for this examination.

IIIII II I III g I'I

'III J

/ I I

I

+I

/

I I

I I

I I

I I

I II,S4 S4 I.S4 Fl.ANGE REACTOR PRESSURE VESSEL SCARCN UNIT NOOVLS FIGURE 2.

BEAM PATHS USED TO EXAMINE THE REACTOR PRESSURE VESSEL-TO-FLANGE WELD b.

Reactor Pressure Vessel Closure Head-to-Flange Circum erential Weld.

The Reactor Pressure Vessel Closure Head-to-Flange Weld was examined ultrasonically from the head shell outside surface (see Figure 3).,

This examination was performed manually using 0-deg longitudinal wave and 45-and 60-deg shear wave search units.

Of the weld length, 33-1/3 per-cent was examined (from centerline of stud hole No.

1 to centerline of stud hole No.

19) in accordance with the requirements of the ASME Section XI.

St. Lucie Plant Unit 1 calibration standard No. 7-CSCL-39-SLC was used to calibrate for this examination.

WSLO Q WSLO SCAN 4

LONO 40+ SNSSR 4S+ SeCJR WLLO g FIGURE 3.

BEAM PATHS USED TO EXAMINE THE CLOSURE HEAD-TO-FLANGE WELD

~

~

c.

Reactor Pressure Vessel Closure Head Studs.

Visual, fluorescent magnetic particle, and manual ultrasonic examinations were per-formed on Reactor Pressure Vessel Closure Head Stud Nos.

6 through 23 and spare stud No. 45 (see Figure 4).

The fluorescent magnetic particle examinations were performed using magnetic particle suspensions from pressurized cans.

Observations for indications were made with the aid of black light rays.

This examination was performed in accordance with the NRC (formerly AEC) Regulatory Guide 1.65.

The ultrasonic examinations were performed with the SwRI stud device which employs a 60-deg shear wave unit.

SwRI calibration standard No. 6-1-8-CS-2 was used to calibrate for these examinations.

A P-number comparison between the studs and the UT calibration standard used is not possible because the stud material is not listed in the P-Number Classification in the ASME Section IX.

However, it was quite apparent to the experienced Level II examiner at the time of the examination that, due to the acoustic properties of the studs and based on the reflections from the machined threads, the examinations were more critical than had a calibration standard of the same material been used.

(y d.

Reactor Pressure Vessel Closure Head Nuts.

Visual, manual liqui penetrant (as required by the NRC - formerly AEC - Regulatory Guide 1.65),

and manual ultrasonic examinations were performed on Reactor Pressure Vessel Closure Head Nut Nos.

6 through 13, S-l, and 15 through 23, and on spare nut, Nos.

121 and 122 (see Figure 4).

Due to visual indications found on nut No. S-l, an additional number of nuts were examined visually (nut Nos.

24 through 31= and 33 through 42) as paragraph IS-244 of the ASME Section XI requires.

The ultrasonic examinations were performed utilizing 0-deg longitudinal wave and 45-deg shear wave search units.

SwRI calibration standard No. 8.5-6-8-CS-2 was used to calibrate for this examination.

FIGURE 4.

CONCEPTUAL DRAWINGS SHOWING EXAMINATION OF RPV CLOSURE HEAD NUT AND CLOSURE HEAD STUD A P-number comparison between the nuts and the UT calibration standard used is not possible because the nut material is not listed in the P-Number Classification in ASME Section IX.

However, it was quite apparent to the experienced Level II 25

~ ~

examiner at the time of the examination that, due to the acoustic properties of the nuts and based on the reflections from the machined threads, the exami-nations were more critical than had a calibration standard of the same material been used.

e.

Reactor Pressure Vessel Flange Li aments.

The Reactor Pressure Vessel Flange Ligament areas from centerline of stud hole No.

1 to centerline of stud hole No..19 were examined ultrasonical'ly (see Figure

5) using a 0-deg longitudinal wave search unit.

SwRI calibration standard No. 6-1-8-CS-2 was used to calibrate for this examination.

SEAL SURFACE SEARCH UNIT Search Unit Seal Surlace STUO HOLES Ligament Area Stud Holes LIGAMENT AREA REACTOR PRESSURE VESSEL FIGURE 5.

REACTOR PRESSURE VESSEL FLANGE LIGAMENTS f.

Reactor Pressure Vessel Closure Head Nashers.

Visual and manual liquid penetrant examinations were performed on Reactor Pressure Vessel Closure Head Large i7ashers and Small Nashers Nos.

64 through 81 and spare Large and Small Washers No. 118.

The manual liquid penetrant examinations were performed in order to satisfy the requirements of the NRC (formerly AEC) Regulatory Guide 1.65.

g.

Reactor Pressure Vessel Closure Head Claddin Visual and manual liquid penetrant examinations were per orme on two 6 x 6-in. areas of cladding on the inside of the closure head.

The areas selected for examination were centered behind stud hole No, 1 for patch No.

1 and No.

5 for patch No.

2, and the bottom of the patches was 8 in. directly above the closure head flange face.

26

2.

Pressuri zer a.

Pressurizer U

er Shell Course-to-U er Head Weld.

Visual and manual ultrasonic examinations were performed on the Upper Shell Course-to-Upper Head Weld.

A 15-in. section of weld from 50 to 65 in. clockwise from the center-line of the manway (0-deg of vessel) was examined.

This examination covered more than the 5 percent of the total weld length required by Section XI.

The ultrasonic examination was performed using 0-deg longitudinal wave and 45-and 60-deg shear wave search units.

Calibration standard No.

TP-PL-S.OO-CSCL-15 was used to calibrate for this examination.

b.

Pressurizer Nozzle Inside Radius Sections.

The Nozzle Inside Radius Sections of the Surge Nozzle and Safety Nozzle A were examined.

The examinations were performed using a 34-deg refracted longitudinal wave search unit.

The calibration for this examination was performed by utilizing the reflections from the nozzle inside radius cladding.

c.

Pressurizer Heater Connections.

All 78 heater connections were examined visually to satisfy the FPL's Turkey Point Plants Units 3 and 4

Technical Specifications.

Heaters with indications were dispositioned by FPL personnel thus closing the appropriate CNF.

d.

Pressure-Retaining Boltin --Manwa Closure.

Visual examinations were performed on the first five of the pressure-retaining bolting (counting counterclockwise from the top of the manway) of the Pressurizer Manway Closure Plate.

The bolting was examined in place and under tension.

e.

Pressurizer Su ort, Bottom Head-to-Skirt Weld.

The Pressurizer Bottom Head-to-Skirt Weld was examined using visual and manual ultrasonic techniques.

A 36-in. section of weld from 248 to 284 inches clockwise from the centerline of the manway (0-deg of vessel) was examined.

This examination covered more than the 10 percent of the total weld length required by Section XI.

An examination from both sides of the weld is not possible due to the existing insulation ring above the weld; The ultrasonic examinations were performed using 0-deg longi-tudinal wave and 45-and 60-deg shear wave search units.

SwRI calibration standard No. PL-CS-1.515-46 was used to calibrate for this examination.

3.

Steam Generator Nozzle Inside Radius Sections.

The Nozzle Inside Radius Sections of the Primary Inlet and Outlet Nozzles were examined applying manual ultrasonic techniques.

The examinations were performed using 39-deg refracted longitudinal wave search units.

The calibration for this examination was performed utilizing the reflections from the nozzle inside radius cladding.

4.

Re enerative Heat Exchan er a.

Re enerative Heat Exchan er, Shell I, Lu The welded support lug on Shell I of the Regenerative Heat Exchanger was examined using visual and manual liquid penetrant techniques.

Ultrasonic examination of this weld is not feasible due to the configuration of the weldment, which is a fillet-type weld attachment.

27

~'

b.

Re enerative Heat Exchan er, Shell I, Cla Restraint.'he Clamp Restraint RGX-I -CR, o

Shell I o the Regenerative Heat Exchanger, was examined visually to comply with FPL's Turkey Point Plants Units 3 and 4 Technical Specifications.

5.

~Pi in a.

Main Reactor Coolant.

Loop "A" welds Nos.

RCC-(A)-4 and RCC-(A)-5 were examined using visual, manual liquid penetrant, and manual ultra-sonic techniques.

Due to visual indications observed on weld No. RCC-(A)-5, an additional number of welds

[weld Nos.

RCC-(B)-4 and RCC-(B) -5] were examined visually, as Paragraph IS-244 of the ASME Section XI requires.

Manual ultrasonic examinations were performed on. the welds

'tilizing 0-deg longitudinal wave and 45-and 60-deg shear wave search units.

Calibration standard No. TP-MRCL-2.437-SS-13 was used to calibrate for these examinations.,

Section XI'ode) were examined visually in the following lines:

2-in.

Remote Thermal Detector Loop "A" Hot Leg (2)

(3)

(4) 2-in. Remote Thermal Detector Loop "B" Cold Leg 4-in. Pressurizer Spray Loop "B" 4-in. Pressurizer Spray Loop "C" (5) 3-in. and 4-in. Pressurizer Relief (6)

(7) 2-in. Boron Injection Loop "B" 2-in. Boron Injection Loop "C" 2-in. High Head Safety Injection Loop "B" and Crossover 3-in. Charging Loop "C" (10) 3-in. Charging to Valve 312C (11) 2-in. Letdown Loop "B" (12) 2-in.

Letdown to Three Orifices (13) 2-in. Seal Injection Loop "A" (14) 2-in. Seal Injection Loop "B" Due to visual indications observed on a restraint in the 3-in.

Charging to Valve 312C line, additional restraints were examined'in this line.

28

The additional examinations revealed that another restraint in the line had indications.

At that point and in order to comply with the FPL's Turkey Point Plants Units 3 and 4 Technical Specifications and Paragraph IS-244 of the ASME Section XI requirements, all of the restraints in the charging lines(1) 3-in.

Charging. Loop "A", (2) 3-in. Charging Loop "C", and (3) 3-in. Charging to Valve 312C were examined visuall'y.

No recordable indications were observed during these examinations.

6.

Reactor Coolant Pum s a.

Reactor Coolant Pum A.

The Seal Housing Bolting, Pump Support No.

1, and Pump Support Structures Nos.

1, 2, and 3 were examined visually.

In

addition, Pump Support No.

1 was examined by manual liquid penetrant techniques because an ultrasonic examination of the Pump Support is not feasible due to high attenuation properties of the mater'ial and geometric configuration of the area.

b.

Flywheels.

hianual ultrasonic examinations were performed from the top surface ~othe flywheel s of Reactor Coolant Pumps A,

B, and C, in place..

To detect indications at the bore,

keyways, and tapped holes of the flywheels, 0-deg longitudinal wave and 45-deg shear wave search units were used.

Calibra-tion was performed by observing the reflections from the keyways of each flywheel.

This examination was performed in accordance with the FPL's Turkey Point Plants Units 3 and 4 Technical Specifications.

29

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