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, other reexamined reportable the area, indications and were found it observed.

to be acceptable. No 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 ~ ~ ~ ~ 1 A. Examination Areas ~ t ~ ~ 1 B. Summary of Examination Results. ~ ~ ~ ~ 2 II. DISCUSSION ~ ~ ~ ~ 5 A. Ultrasonic Equipment ~ ~ ~ ~ 5 B. Recording Criteria ~ ~ ~ ~ 5 C. Radiation Exposure ~ ~ ~ ~ 6 III. NONDESTRUCTIVE EXAMINATION

SUMMARY

TABLE ~ ~ ~ ~ 7 A. Examination Area Identification Column ~ ~ ~ ~ 7 B. Examination Method Column , ~ ~ ~ ~ 8 C. Indications Columns ~ ~ ~ ~ 9 D. Remarks Column ~ ~ ~ ~ ~ ~ ~ ~ ~ 10 E. Table . ~ ~ ~ ~ ~ ~ ~ ~" ~

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

~ Heater Connections Re enerative Heat Exchanger

~ Clamp Restraint

~Pi ing

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

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

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

~ 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 Injection Loops "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"

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

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

~ 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.

~ 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'lINATION SPi0iARY 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 opposed to being numbered as the first weld on the branch line.

's 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 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 t

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- I II],

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

FIGURE 2 Pictorial Representation of Root Indication

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TURK'EY I'OINT I'LANT UHlT 3 1976 iHSL'RVICE IIXISIIHATlOH SUMIARY OF HOHDESTRUCTIVL'XiQIIHATIOHS PRFSSURI ZER Scc Ai ondix A Fi uros A-2 and A-3 ASME ASME Swill WELD INDICATIONS EXAh'IINATION SEC. XI SEC. XI 'IIOCEDUA EXAM.SUhI - BEhIARKS ITEMNO CATGY.

AAEA IDENTIFICATION NO.IAEV. SHEET NO. NO IIECORDAULE INSIGNIFICANl GEOhIETAIC OTHER 2.4 P.-2 llcatcr Connections VT 900-1/22 300099 Hos. 1 through 78 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 ASM E Swfll WEhP INDICATIONS SEC. XI SEC. XI EXAMINATION AIIEAIDENTIFICATION MCTIOD

'" IIEMARKS ITEMNO CATGY. NoanEV. SIIEETNO. NO AECOIIDABLE INSIGNIFICANl GEOMETIUC OTIIEII RGX-(I)-CR VT 900-4/10 300056 Clamp Restraint

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

ASME ASM E SwAI WELD INDICATIONS EXAMINATION EXAM.

SEC. XI SEC. XI AOCEDUAI EXAM.SUM REMARKS CATGY. AREA I DE NTI F I CATION METHOD NO.IAEV. SHEET NO. NO AECOAOAOLC INSIGNIFICAN GEOMETAIC OTHEA ITEMN 29" ID IICC-(8)-2 900-1/22 300157 hrc Strike. Scc CNF 4100369.

Pipe-to-Pipe Rcmovcd by lifht polishing. Reex-amination was pcrformcd by FI'I.

personnel.

600-3/28 0 I,45 T 45 45 Three 45'ndications duc to crown

w. dev. 60 geometry. Two 45'nd two 60 in-I 8 2 dications duc to metallurgical intcrfacc. Scc Indication ltcso-lutlon Record 4310009.

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

3.3 RCC-. (8) -4 VT 900-1/22 300135 X configurat-Elbow-to-Hozzle Ir 200-1/22 X Iff 600<<3/28 0 L,O W,45 Ho examination from thc downstream

w. dcv. 45 T,GO side due to thc nozzle I fj 2 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 Vf 900-1/22 300136 X Nozzle-to-Elbow PT 200-1/22 X Ilr 600-3/28 0 LIO N045 0 Ho oxamlnation from thc upstream w, dcv, 45'T,60 side duc to the nozzle configura-Ifj2 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 ASME SwAI WELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

ROCEDUR EXAM.SUh)

ITEh) NO CATGY. Af)EA IDENTIFICATION METIIOD RE)IARKS NO7REV S))EET NO. NO RECORDABLE INSIGNIFICANl GEOMETRIC OTIIE 0 4.8 J-I G VT 900-1/22 '00029 X Valve-to-Pipe PT 200-1/22 X 4.6 K-2 6-PR 900-4/10 3000B9 Scale rcadina: Indicator at lock Pipo Restraint bolt hole lovel. Scc CNF S)00355.

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

i~ 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 ASME SwRI WELD INDICATIONS EXALIINATION SEC. XI SEC. Xl ROCEDUR EXAhI.SULI RELIARKS AREA IDENTIFICATION LIETHOD ITEhI NO CATO Y. SHEET NO. NO RECORDABLE INSIGNIFICANT GEOMETRIC OTHER 4,8 J-I 6 000-1/22 Zn0021 Valve-to-PIpe 200-1/22

TURKEY I'OINT PLANT UNIT 3 197G INSERVICE EXAHINATION SI08fhRY OF NONDESTRUCTIVE EXQIINATIONS 2" RTII IIOT IJ!G IQOP nAn Sec A~ cndix A Fi ore A-15 ASME ASME SwAI WELD I NO I GATI 0 NS EXAMINATION EXAM.

SEC. XI SEC. XI 'AOCEDUA EXAM.SUM REMARKS AAEA IDENTIFICATION ITEM NO CATGY. NO.IAEV. SIIEET NO. NO AECOADAOLE INSIGNIFICANl GEOMETAIC OTIIEA 4.G I;-2 IO-PR-0 VT 900-4/10 3000GS Scale reading at lock holt hole Pipe Rcstr'aint level. Sce CHF II00348.

Accepted "as is" by FPI. Personnel.

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

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 SnRI WELD INDICATIONS EXAhIINATION 'AOCEOUA EXAhl. SUM SEC. XI SEC. XI REM ATIKS AIIEAIOENTIFICATION NO.IAEV. SIIEET NO. NO nECOnOAELE INSIGNIFICAN'I GEOAIETAIC OTIIEII ITEMNO CATGY.

4.8 7 VT 900-1/22 300066 Pipe-to-Valve PT 200-1/22 4 ' 12 VT 900-1/22 300005 Coupling-to-Pipe PT 200-1/22 15 Vl'T 900-1/22 300006 I'ipc-to-Elbow 200-1/22 4.8 20 Vl'T 900-1/22 300007 Pipe-to-Tce 200-1/22 4 ~4 G-2 238L VT 900-1/22 300137 Eight bolts and sixteen nuts Flange Bolting examined in place.

4.6 K-2 30-PR-A VI'00-4/10 300067 1/4" space between U bolt ahul Pipe Restraint pipe. Sce CHF 1100344.

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

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

TURKEY POINT PLANT UNIT 3 19m INSERViCB BXANINATION SIDDIARY OF NONDESTRUCTIVE I:.KAIIINATIONS 2" RTI) IIOT IJ!G I.OOP "C" Scc A endix A Fi uro A-D ASME AShIE SwAI WELD INDICATIONS EXAMINATION SEC. XI SEC. XI 'AOCEDUA EXAM.SUh'I AEhIAAKS AAEA IDENTIFICATION ITEMN CATGY. NOJAEV. SHEET NO. NO AECOADADLE INSIGNIFICAN1 GEOMETAIC OTHEA 4.8 900-1/22 300022 Elbow to-Pipe 200-1/22 4.8 14 900-1/22 300010 Pipe-to-Valve 200-1/22 4.8 19 900-1/22 300089 Flange-to-Pipe 200-1/22 4.4 19DL VT 900-1/22 300138 Bight bolts and sixtocn nuts Flange Dolting examined in place.

K-2 2G-PR-D VT 900-4/10 300068 U bolt bracket bent and mis-Pipe Rostraint aligned with holdor. Scc CNF k100341.

U bolt was aligned nnd holder tightened by FPL pcrsonncl.

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

i. ~ TUIIKEY I'OINT I'LAtff UNIT 3 1970 \NSEIIVICE I!XISIINA'flOttSINIILAIIYOF t)ONQIISTNlCTIVII PXAIIIIIATIONS 0 Cnl.n .I!B IA)QP u " Se - 8 AShlE AShlE SwBI WELD INDICATIONS EXAMINATION EXAM. 'BOCEDUBI EXAM.SUM SEC. XI SEC. XI BEhlABKS ABEA IDENTIFICATION NOJBEV. SIIEET NO. NO BECOBDADLE INSIGNIFICAN) GEOh)ETBIC OTIIEB ITEMNO CATGY.

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

TURKEY POINT PLANT U>>1T 3 1976 i>>SERViCB BKANI>>ATlO>> SeSIART OF >>0>>IIImnUCT1VB FXAW1>>AT10>>S 2" RTA COI.D .EG tare n8>> Sce A andix A Fi uro A-19 ASME ASME SwAI WELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

AOCEDUA EXAM.SULI AEMAAKS AREA IDENTIFICATION. METHOD ITEMNO CATGY. NOJAEV. SHEET NO. NO AECOADADLE INSI G >>IF I CANl GEOMETAIC OTHER 4.8 5 VT 900-1/22 300062 Pipe-to-Plbow PT 200-1/22 4.6 K-2 7-PR-8 900-4/10 300139 I'lpe Restraint 4.8 8 9DD-1/22 300063 Elbow-to-Pipe 200-1/22 4.6 K-2 17-PR-B 900-4/10 300064 Broben restraint. Sce C>>F l100340.

Pipo Restraint Restraint was repaired by APE personnel.

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

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

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POINT Pmrr IINIT 3

'unfrV 1976 INSFIIVICE EXAlllNA'flON SIIWIAIIY OP NONIIfMIIUCflYf:IIXAIIlNATlOILS 2" RTB COI.D IlIG lOOP "C" Sco A >)endix A Pi ure A-20 AShIE ASh1E SwBI WELD INDICATIONS SEC, XI SEC. XI EXAh1INATION EXAM.

'BOCEDUB EXAM. SUM ITEh1NO CATGY. ABEA IDENTIFICATION METIIOD BEhIABKS NO IBEy. SIIEET NO NO BECOBDAELE INSI GNI F I CANT GEOMETBIC OTIIEB

~ I~8 J-1 2 VT 900-1/22 300008 Pipe-to-Elbow P.T 200-1/22 8.8 J-1 5 900-1/22 300009 Valve-to-Pipe 200-1/22 z.s J-1 15 900-1/22 300026 flbow-to-Pipo 200-1/22 4.8 29 900-1/22 300019 Elbow-to-Pipe 200-1/22 J-1 36 VT 900-1/22 300020 Pipe-to-Reducer PT 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 ASME SvrAI IVELD INDICATIONS EXAMINATION EXAh'I.

SEC. XI SEC. XI 'ROCEOURI EXAhl. SUM REhIARKS AREA IDENTIFICATION hIETIIOD ITEh1NO ~A TGY. NO.IREV. SIIE ET NO. NO RECORDABLE INSIGNIFICAN1 GEOMETRIC OTIIER 4.1 lA VT 900-1/22 300141 X Hottlo-to-Safe-End PT 200-1/22 X UT 600>>3/28 O'L,O',45'5 Ho examination fron thc upstream

w. dcv. T,60 side duo to tho nettle confitprration.

1 f,2 Cal. Std. TP-4-120-.438-SS-4.

4.2 J-I 7 900-'1/22 300013 X Pipe-to-Pipe G00-3/28 0 1.,45 Cal. Std. TP-4-120-.438 I.

M, dcV 45 T,60 1 6 2

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 ASh'IE SwAI 'IVELD INDICATIONS SEC. XI SEC. XI EXAMINATION

'AOCEDUA EXAhl. SUM ITEM NO CATGY. AREA IDENTIFICATION hIETIIOD AEhlAAKS NO.IAEV. SIIEET NO. NO RECORDABLE INSIGNIFICAN1 GEOMETAIC OTIIE 4.2 J-I I Elbow-to-Pipe 900-1/22 600-3/28

w. dov.

142 300014 60'5X O'L,45'T, 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 ASIAE SwAI 'LVELD It<OICATIONS EXAMINATION SEC. XI SEC. XI AOCEOIjAI EXAM.SUM AEMAAKS AAEA IDENTIFICATION ITEMN CATGY. NO.IAEV. SIIEET NO. NO AECOAOABLE INSIGNIFICAN GEOMETAIC OTIIEA 4.2 J-I 5 900-1/22 300015 X Pipe-to-flboM 600-3/28 041.,454, Col. Std. TP-4-120-.438-SS-4.

wo dove 45'T,60 I Pj 2

2~ M ~,

TURKEY I'OINT PihttT UNIT 3 1976 IttSL'RVICE EXANINATION SQIIIARY OP ttOIIAESTRUGfIVE I!XAIIlttATIOIIS 4" PRESSURIZER SI'RAY LOOP "8" (Sco Appendix A, Figuro A-25)

ASME ASME Swnl WELD INDICATIONS EXAMINATION 'AOCEDUAI EXAM.SUhI SEC. XI SEC. XI nEMAnKS ITEhINO CATO Y.

AREA IDENTIFICATION NOJAEV. SNEET NO. NO AECOADABLE INSIGNIFICANl GEOh'IETAIC OTHEA 1.2 9 900-1/22 300156 Iitbow-to-Pipe 600-3/28 0 L,45 Ho examination upstream from 1-3/4" w dev, 45 T,60 to 7-1/8" duc to elbow curvature.

Itj2 Cal. Std. TP-4-120-.438-SS-4.

1.G K-2 9-PR-C Vr 900-4/10 300090 Angle iron restraint misaligncd.

Pipe Restraint Sec QIP t100343.

Acccptcd "as ls" by FPI. personnel.

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

Pipe Restraint Sco QIP f100342.

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

4.G K-2 13-PR-G Vl'00-4/10 300092 X ScAle roading: 0u. Scc Pipe Restraint QIF l 100349 ~

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

K-2 15-PR Vf 900-4/10 300093 Scalo reading: 4-7/8". Scc Pipe Restraint QIF I100351 ~

Accepted "as is" by FPL pcrsonncl.

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

'lllltKI<Y POIIff PIJQff UNIT 3 1976 IHSERVICB IIXAIIIHA'f ION SUWIAIIY OF NQIUESTRUCfIVU RXAIIINATIOHS 4" PIIPSSURIZEII SPItAY IAXIP "C" Sce A cn<lix A Fi ure A-26 ASME ASME Swnl WELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

ROCEDUR EXAM.SUM ITEMNO CATGY. AREA IDENTIFICATION METHOD REMARKS NOJREV. SIIEETNO. NO RECORDABLE IN S IGNI F I CAN1 GEOMETRIC OTIIER K-2 2-PR-I 900-4/IO 300095 I'ipc Restraint reading: 2-1/4". Scc CNI u 100356.

Accepted "as is" by FPI. pcrsonncl.

K-2 2-PR-2 900-4/10 300096 Scale reading: 3-1/4". Scc Pipe Restraint CHF I100350.

Acccptcd "as is" l>y FPL personnel.

4.2 8 900-1/22 300142 Arc strikes, gouges, and grind-lllbow-to-Pipe ing marks. Sec CHF el00372.

Indications removed by grinding.

Reexamination was performed by FPL personnel.

00-3/28 Ho examination from thc upstream

.dev. side from 10-1/2" to 12-12" duc I f< 2 to thc elbow inner radius.

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

K-2 8-PS-D 00-4/10 300031 Pipe Support Structure 4.6 K-2 10-PR-J 00-4/10 300097 O'L,45'5'T,60L,45'5'T,60' Scale reading: 3". Scc CNF S 100353.

I'ipe Restraint Accepted "as is" by FPI. pcrsonncl.

4.2 13 00-1/22 300143 Arc strikes: Scc CNF I100373.

Pipe-to-flbow Indications removed by grinding.

Rccxamination was pcrformcd l>y 00-3/28

. dcv.

O'I.,O'II,45'5'T,60'cale FPL pcrsonncl.

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

I f>2 4.2 18 00-1/22 300017 Valve-to-Pipe 00-3/28 No examination from the upstream

. dcv. side due to thc valve configuration.

I 8 2 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. 0, TURKEY POINT I'I&IT UNlT 3 1976 INSBRVICB BXAIIINATIOHSUIIIiARY Ol'ONDESTRUCTIVE IIXi@IIHATlOHS 4" I'RBSSURIZBR RBLlEF'ec A endix A Fi urc A-27 ASME ASME SwRI WELD . INDICATIONS EXAMINATION EXAhl.

SEC. XI SEC. XI 'ROCEDUR EXAM. SUhl REhIARKS AREA IDENTIFICATION METHOD ITEM NO CATGY. NO.IREV. SHEET NO. NO RECORDABLE INSIGNIFICANT GEOMETRIC OTHER 1A 900-1/22 300144 X Nozzle-to-Safe Bnd 200-1/22 X 600-3/28 '.,O'II,45, No examination from the upstream

w. dev. 45'T,60 side due to thc notxlc configuration.

1 f(2 Cal. Std. TP-4-120-.438-SS-4.

4.2 3 VT 900-1/22 300155 Arc strikes, gouges, and wcl'd spatter.

Elbow-to-Pipe See CNF f100380. Indications rc-movcd after grinding. Reexamination 600-3/28

w. dev.

0 L,45 T 45'0 was pcrformcd by I'Pl, personnel.

Two indications due to crown geometry.

Scc Indication Resolution Record I f(2 g310006.

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

4.6. K-2 7-PS 900-4/10 300101 Pipe support structure disconnected.

Pipe Support Structure Scc CHF I100368.

Support rcconncctcd by FPI. pcrsonncl.

4.6 K-2 8-PS-1 900-4/10 300102 Pipe support structure disconnected.

Pipe Support Structure 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 ASME S00B I WELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

'AOCEDUA EXAM.SUM ITEM NQ CATGY. AREA IDENTIFICATION METHOD AEMAAKS NO.IAEV. SI IE ET NO. NO AECOBDAGLE INSIGNIFICAN1 GEOh'IETBIC OTIIEB 4.2 2 900-1/22 300145 strikcs0 gougcs0 and wold Elbow-to-Elbow spatter. See CHF 1100370.

Indications rcmovcd after grinding.

Reexamination was performed I>y FI'L personnel.

600-3/28 O'L,45', Cal. Std. TP-3-1G0-.438-SS-2.

w. dov. 45 T060' 1 f02 45'T,60'rc 4 ~2 8 900-1/22 300154 Are strikes, gouges, and wold Elbow-to-Elbow spatter. Sco CNF 0100371.

Indications rcmovcd after grinding.

Rccxamination was performed by FPL personnel.

600-3/28 L045 Cal. Std. TP-3-160-.438-SS-2.

wo deva 1 F02

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

ASMC ASME SwfU WELD INDICATI0 NS EXAMINATION EXAM. >AOCEDURI SEC. XI SEC. XI EXAM.SUM AEh1ABKS AAEA IDENTIFICATION METHOD NO./IIEV. SHEET NO. NO RECOIIDAOLE INSIGNIFICAN GEDMETRIc QTHEA ITEh1NO CATGY.

4 6 K-2 4-PR-S 900-4/10 300103 Scalo reading: 7-1/2". Scc Pipo Restraint CNF I100365.

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

4.6 K-2 6-PR 900-4/10 300050 Pipe Restraint 4.G K-2 8-PR 900-4/10 300049 Scale roading: 2". Sco Pipe Restraint CHF 8100352 "as ccepted is" by I'I'I. Personnel.

4.G K-2 13-PR-N 900-4/10 300048 Scalo reading: 3/4". Sec Pipe Rostraint CNF f100354 ~

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

4.8 14 Vf 900-1/22 300057 Pipe-to-Elbow PT 200-1/22 Linear indication. Sce CHF II00357.

Indication removed by light grinding and polishing. Reexamination was performed by FPI. Personnel.

4.8 19 900-1/22 300061 X Elbow-to-Pipe 200-1/22 X 4.6 K-2 20-PR-ll 900-4/10 300104 U bolt untightencd. Sec I'ipe Restraint CHF 8100362.

U bolt was replaced by FPI, personnel.

4.8 30 VT 900-1/22 300105 Pipe-to-Elbow PT 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 SwRI WELD INDICATIONS SEC. XI SEC. XI EXAMItIATION

'ROCE DUB EXAtiI.SUII ITEMNO CATGY. AIIEAIDENTIFICATION AfMAIIKS NO.IAEV. SHEET NO. NO AECOADADLE INSIGNIFICANl GEOAIETRIC OTIIER 4 6 K-2 6-PR-A VT 900-4/10 300036 Pipe Restraint

TUIU'I!Y 03 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 SwRI WELD UJDICATIONS EXAMINATION EXAh'I.

SEC. XI SEC. XI ROCEQURI EXAhI.SUM REhLARKS AREA IDENTIFICATION METIIOD ITEMNO CATGY. NOJREV. SHEET NO. NO RECORDABLE INSIGNIFICANT GEOhIETRIC OTHER 4.G "K-2 8-PS-D 900-4/10 300037 Pipe Support Structure

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 SwAI YIELD INDICATIONS E'XAMINATION EXAM. 'AOCEDUA SEC. XI SEC. XI EXAM.SUM AEhIAAKS AREA IDENTIFICATION METIIOO ITEMN CATGY. HOJAEV. SIIEET NO NO RECORDABLE INSIGNIFICAN GEOMETRIC OTIIEA 4 ' J-I 16 VT 900-1/22 300106 Pipe-to-Elbow PT 200-1/22 4.6 K-2 IG-PR-I 900-4/10 300085 Restraint bent. See CHF ll00315.

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

4~6 K-2 20-I'R- J 900-4/10 300038 I'ipo Restraint 4.G K-2 20-PR-K 900-4/10 300039 Pipe Restraint 4 ' K-2 24-PR-3 900-4/10 300051 Pipe Restraint 4.8 27 900-1/22 300107 X Valve-to-Pipe 200-1/22 X 4.6 K-2 31-PR-II 900-4/10 300052 Pipe Restraint

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 ASM E SwAI 'IVELO INDICATIONS EXAMINATION M SEC. XI SEC. XI BOCEOUAI EXAM.SUM REMARKS AREA IOENTIFICATION NO.IAEV. SIIEET NO. NO AECOROADLE INSIGNIFICANI GEOh'IETAIC OTIIEA ITELINQ CATGY.

J-1 4 900-1/22 300108 Pipe-to-Elbow 200-1/22 4.8 J-I 8 900-1/22 300109 Pipe-to-Elbow 200-1/22 4.8 J-I IG 900-1/22 300110 . X Pipe-to-Elbow 200-1/22 X 4.8 J-I 28 900-1/22 300111 X Pipe-to-Elbow 200-1/22 X

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

ASME ASh'IE SwRI ~ WELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXALI.

'AOCEDUII EXAhl. SULI ITEMNO CATGY. AAEA IDENTIFICATION METIIOD REMAIIKS NOJIIEV. SIIEET NO. NO IIECOADAOLE INSIGNIFICAN1 GEOMETRIC OTIIE 8 4.8 4 Vl'T 900-1/22 300112 Pipe-to-Ell>ow 200-1/22 4~8 9 Vf 900-1/22 300113 Elbow-to-Pipe PT 200-1/22 K-2 14-PR-E 900-4/10 300086 Pipo not secured by U bolt. Scc Pipe Rostraint r100338.

'HF U bolt was rcplaccd by Fl'I. pcrsonncl.

4.8 22 Vl'T 900-1/22 3001'14 Pipe-to-Elbow 200-1/22 4.8 29 900-1/22 300115 Arc striko. Scc CHF I100377.

Valve-to-Pipe Indication was rcmovcd by light grinding. Rcoxamination was performed by FPL pcrsonnol.

PT 200-1/22

~,

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

ASME ASME Swnl WELD INDICATIONS EXAMINATION EXAhl.

SEC. XI SEC. XI AOCEDU A EXAhL SUM AEhlAAKS AAEA I DENT IF I CATION METHOD ITEhl NO CATGY. NO IAEV SIIE ET NO. NO AECOADABLE INSIGNIFICAN1 GEOMETAIC OTHE 4.2 2 VT 900-1/22 300146 strikes, gouges, and pits.

Tee-to-Pipe Seo CNF I1003?9.

Indications rcmovcd by light buffing.

45'5'rc Rccxamination was performed l>y Fl'L personnel.

UT 600 3/28 0 LJO IV, Limited examination upstream I'rom w dev, 45 T,60 ll" to 3" due to tce configuration.

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

4.6 K-2 7-PR-A VT 900-4/10 300147 Pipe Restraint 4.2 9 900-1/22 300148 X Pipe-to-Elbow 600-3/28 O'L,45'T, Limited examination downstream

w. dcv. 60 from 4-1/4u to ?-I/2" due to I Q2 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" IIIAI IIEAD SIS lAMP "8" (Seo Appendix A, Figure A-37)

ASME ASI IE Swnl WELD INDICATIONS SEC. XI EXAMINATION SEC. XI AOCEOUAI EXAM.SUh'I AEhlAAKS AREA ID' NT IF I GATION ITEhlNO ~MTGY. NOJAEV. SIIEET NO. NO AECOADABLE INSIGNIFICANl GEOMETAIC OTIIEA 4.8 7 900-1/22 300116 Pipe-to-Valve 200-1/22 4.6 7-PR-GG VT 900-4/10 300053 Pipe Restraint 4.8 12 900-1/22 300117 X Elbow-to-Pipe 200-1/22 X 4.8 32 Vf 900-1/22 300118 Pipe-to-Elbow PT 200-1/22 4,6 K-2 38-'PR-Tl VT 900-4/10 300033 Pipe Restraint 4.6 K-2 40-I R-S VT 900-4/10 300054 Pipe Restraint 4.8 J I 43 Vl'T 900-1/22 300119 Elbow-to-Pipe 200-1/22

TURKI!Y POINT PIJUIT UNIT 3 1976 INSLRVICII L'Xi5IIHAT10N SUhflARY OP HOHDIM'RUCTIVII IIXAI41HATIONS 2" lllAI HEAD SIS CROSSOVER Soc A icn0ix A Fi uro A-37 AShIE ASME SwrIII 'LVELD INDICATIOI4S EXAhllNATION EXAM. 'ROCEDURI SEC. XI SEC. XI EXAM. SUM REMAIIKS ITEMNO CATGY.

AIIEAIDENTIFICATION hIETIIOD NO.IAEV. SHEET NO. NO IIECOBDABLE INSIGNIFICAN1 GEOhIETAIC OTIIEA 4.8 J-i 3 900-1/22 300120 X Pipe 200-1/22 X 900-4/10 300041 to-Bib'-l'R-I'ipo 4.6 K-2 Rostraint 4,6 K-2 7-PR 900-4/10 300040 Pipe Rcstroint

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

ASME AShIE SwAI WELD INDICATIONS E'XAhII NATION EXAM.

SEC. XI SEC. XI AOCEDUA EXAII.SUM AEMAAKS AREA IDENTIFICATION METHOD ITEMNO CATGY. NO.IAEV. SHEET NO. NO AECOADAOLE INSIGNIFICAN1 GEOhIETAIC OTHER 4.2 J-I 6 Pipe-to-Valve 900-1/22 600-3/28

w. dov.

1 8 2 300149 45'Ti60'o X

O',O'I$ ,45', 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 AShlE SwRI IVE LD INDICATIONS EXAMINATION EXAM.

ROCEDURI EXAhl. SUM SEC. XI SEC. XI REMARKS AREA IDENTIFICATION METIIOD ITEhl NQ CATGY. NO./REV. SIIEET NO. NO RECORDABlE INSIGNIFICAN GEOMETRIC OTHER 4.2 6 900-1/22 300150 Gouge and weld spatter. Scc

)Ill>ow-to-Pipe CNF I)100381.

Indications removed by light filing.

Rccxamination was performed by FPI.

pcrsonncl.

600-3/28 1.,45 f 45 60 Limited examination upstream From w dave ~ 4-1/4" to 7-1/2" due to inner r:>dius I f> 2 of elbow.

One 60 indication duc to root geometry. Scc Indication Resolution Record I310003.

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

4.2 11 900-1/22 300121 X I'ipe-to-Elbow 600-3/28 0 L,45'T, 45 45 Onc 45'ndication d>>e to crown

w. dcv. 60 geometry. Scc Indication Resolution I f> 2 Record l310004.

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

4.2 24 Elbow-to-Pipe 900-1/22 600-3/28 w.

I dcv..

fj 2.

300122 60'5 O'L,45'T, X

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

K-2 25-PR-X 900-4/10 300123 Ilissing clamp bolt. Scale reading:

Pipe Restraint 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 EXAMINATION SU IIIARY Ol'ONDESTRUCTIVE EXANIHATIOHS 3" CIIARCIHC I.INE LOOP "C" (See Appendix A, Figuro A-40)

ASI.IE ASM E SwAI WELO INDICATIONS EXAMINATION EXAM.

SEC. XI SEC. XI AOCEOUA EXAM.SUM REMARKS AREA IDENTIFICATION METHOO ITEMNO CATGY. NOSEY. SHEET NO. NO AECOAOAOLE INSIGNIFICAN1 GEOMETAIC OTHER 4.2 2 900-1/22 300124 X Elbow-to-Pipe 600-3/28 O'L>45'T 454 604 examination upstream from

w. dev. 4-1/4" to 7-1/2" due to inner radius IF>2 of elbow.

One 60 indica'tion due 'to inside surface geometry. Scc Indication Resolution Record s310005.

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

K-2 7-PR-IIN 900-4/10 300088 Pipe Restraint 60'.imitcd 4.2 18 900-1/22 300151 Shallo~ gouges <<ith sharp cdgcs.

Tce-to-Pipe Sce CNF I100374.

1 Indications removed by grinding.

Reexamination was porformcd hy FPL personnel.

600-3/28 O'L,O'W, 45 , 60 Four 45'ndications duc to root

w. dev. 45'T geometry. Onc 60'ndication due to IF>2 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.

4.2 28 900-1/22 300125 X Elbow-to-Pipe 600-3/28 O'L,45'5 Limited examination upstream from

w. dev. T,60 I-I/8" to 7-1(2" due to inner radius IF>2 of elbow.

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

4.2 33 900-1/22 300126 X Tcc-to-Elbow 600-3/28 O'L,45'5 ne 60 indication due to root

w. dev. T geometry. Scc Indication Resolution I f> 2 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 SwBI WELD INDICATIONS EXALUtIATION 'AOC SEC. XI SEC. XI E Ahb DEhIAAKS AB EA I DENT I F I CATIOtt ITEh! tlO CATGY. tIO./REV. SIIEET NO. NO IIECOADADLE INSIGNIFICAttl GEOLIETll!C OTIIEI>

4.6 '-2 44-PR-N Pipe Restraint Vr 900-4/10 300127 Restraint broken. Scc Restraint repaired and CHF lu>sc I10036il.

plate added by Fl'I. pcrsonncl.

K-2 SO-I'R-.l Vf 900-4/10 300128 Drokcn U bolt. l Scc CNF I00359.

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

4.6 K-2 50-PR-G VT 900-4/10 300129 U bolt loose. Sec CHF I II)0367.

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

1.6. K-2 52-Plt-A2 VT )00-4/10 300130 bolt bent and loose. Scc Pipe Restraint CHF II00366.

U bolt replaced and tightened l>y FPL pcrsonnol.

4.2 54 VT )00-1/22 300152 Iield spatter and nrc strikes. Scc Pipe-to-Rlbou CHF 4100375.

Indications removed by light polish-ing. Roexamlnation was performed l>y Fl'L pcrsonncl.

100-3/28 O'L,45'T 45',60' Limited examination upstream from dcv. I" to 4" due to branch connection.

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

4.2 56i 00-1/22 300153 Held spatter. Sco CIU> 1IOD376.

Valve to P>pc Indications removed by I i gh t fi I-ing. 'eexamination was performed l>y FPI, personnel.

00-3/28 0 I.,O',45'5'T,60 tto examination upstream d<<e tn deva valve configuration. I.imitcd cx-I f> 2 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 IIOIIDFSTRIICflVB BXQIINATIOtlS I A I

2" IJTDNIII I.ItlB IAXIP "B" (Soo A ondIX A, Fignro A-42)

ASME AShlE SwR I WELD ItIDICATIONS SEC. XI SEC. XI EXAMINATIOtl 'ROCEDUR EXAh'I. SUM AREA IDENTIFICATION REhlARKS ITEhINO CATGY. NOIRE. SHEET NO. NO RECORDABLE ItISIGNIFICAN GEOMETRIC OTIIER 4.6 f-2 11-PR Vf DOa-4/IO 3OOODS Pipo Rostraint

<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 SwAI lVE LD INDICATIONS EXAMINATION EXAM. SUhl SEC. XI SEC. XI nghlARKS AREA IDENTIFICATION SIIEE'T NO. NO RECORDABLE INSIGNIFICANl GEOh'IETRIC ITEM N <MTGY. No IREV OTIIE 0 4.& 6 900-1/22 300132 X Elbow-to-Pipo 200-1/22 X 4.G K-2 6-PR Vf 900-4/10 300131 U bolt missing and bracket bent.

Pipe Restraint Sco CNFl1003S& ~

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

4.G K-2, 6-PR-A Vf 900-4/10 300070 Pipe Restraint 4.& VT 900-1/22 300047 12'ibow-to-Pip I' 200-1/22 4.6 K-2 12-PR-0 VT 900-4/10 300071 Pipe Restraint 4.& 22 Vf 9ao-1/22 3aoo46 X Tcc-to-Pipe PT 200-1/22 X 4.6 f.-2 24-PR VT 900-4/ IQ 300072 Pipe Restraint 27 VT 900-1/22 300073 Pipe-to-Elbow PT 200-1/22

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 SwRI WELD INDICATIONS EXAMINATION EXAM. ~

SEC. XI SEC. XI ROCEOUR EXAM.SUM REhIARKS AREA IDENTIFICATION hIETHOD, ITEMN CATGY. NO./REV. SHEET NO. NO RECORDABLE INSIGNIFICAN'I GEOhIETRIC OTHER 4.8 6 900-1/22 300074 Pipe-to-Elbow 200-1/22 4.6 K-2 8-PR-0 900-4/10 300158 !kissing support braco bolt. See Pipe Restraint QIF II00337.

Bolt was replaced by FPL personnel.

4.6 14-PR-D 900-4/10 300043 Pipe Restraint 4.& 16 900-1/22 300075 Sharp gougo. Seo CNF I100347, Pipe-to-Elbow Indication was removed after grind-ing. Reexamination was performed by FPL personnel.

200-1/22 Seo cmarks PT was not performed due to sharp gouge and will bo rcschedulod for an upcoming outage.

4.6 20-PR-1 900-4/10 300002 Pipo Restraint 4.8 23 Vf 900-1/22 300044 Elbow-to-Pipe PT 200-1/22 4.6 K-2 24-PR 900-4/10 300045 Pipe Restraint 4.6 K-2 24-PR-1 900-4/10 300076 U bolt loose. Scc QIF ll00339.

Pipe Restraint U bolt replaced and tightened by FPL personnel.

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

~~

TURKEY POIHT PLANI'NIT 3 197G IHSERVICE EXAillNATION,SUIQIARY Op HOHDESTRUCfIVE I!XAhllHATIOHS o II e I x I nre A-45 AShIE ASME Swnl VjtELO INDICATIONS EXAMINATION EXAhl. 'AOCEDUAI SEC. XI SEC. XI EXAM.SUM AEMAIIKS AREA IDENTIFICATION hIETIIOD ITEM NO CATGY. NO.IAEV. Sl IE ET NO. NO RECORDABLE INSIGNIFICAN1 GEOhIETAIC OTIIER 4.G K-2 i3-PR-n 900-4/10 300079 Pipo Rostraint 4.G K-2 13-PR 900-4/10 300078 Pipe Restraint 4.8 18 VT 900-1/22 300080 Elbow-to-Pipe PT 200-1/22 4.8 28 900-1/22 300081 Pipe-to-Elbow 200-1/22 4.6 K-2 28-PR-1 900-4/10 300082 Pipe Restraint 4.6 K-2 28-PR-2 900-4/10 300133 llanger loose. Sec CHP I1003G4.

Pipe Rostraint 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 ASME SwRI WELD ItIDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

ROCEDUR EXAhI. SUhI ITEM tt CATGY. AREA IDENTIFICATION METHOD REMARKS NO.IREV. SHEET NO. NO RECORDABLE INSIGNIFICAN1 GEOMETRIC OTHE 4.8 J-1 19 VT 900-1/22 300083 Elbow-to-Pipe PT 200-1/22 4.6 K-2 26-PR-C 900-4/10 300055 Pipe Restraint 4.8 J-1 29 VT 900-1/22 300084 Valve-to-Pipe PT 200-1/22 4.6 '-2 32-PR-E 900-4/10 300034 Pipe Restraint

ATTACHMENT B 1976 INSERVICE EXAMINATION OF CLASS I COMPONENTS AT

'4 TURKEY POINO PLANTg UNIT NO 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

~Pa e Mi'IT 4 - FINAL REPORT LIST OF FIGURES ~ ~ 1 LIST OF ABBREVIATIONS ~ ~ 11 I. INTRODUCTION A. Examination Areas l B. Summary of Examination Results ~ ~ 2 I I. NONDESTRUCTIVE EXAMINATION

SUMMARY

TABLE ~ ~ 4 A. Examination Area Identification Column 4 B. Examination Method Column . 4 C. Indications Columns . ~ ~ ~ 6 D. Remarks Column ~ ~ ~ 8 E. Table . ~ ~ ~ ~ ~

~ ~ 8 I II ~ DISCUSS ION o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 23 A. Equipment . 23 B. Examination Details . 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 Head-t'o-Fl ange Nel d ................,

Paths Used to Examine the Closure 24 Conceptual Drawings Showing Examination of Closure Head Nut and Closure Head Stud........

RPV 25 Reactor Pressure Vessel Flange Ligaments........ 26

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

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 Line Loops "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".

II . 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.

Li uid Penetrant t

2. (PT)

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].

b. Lon itudinal Wave Weld Scan (O') . In cases where the (g 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 CROWN PATH 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 ASME SwRI 'LVE LD INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

ROCEDUR EXAM$. SUM REMARKS IT EMN CATGY. AREA IDENTIFICATION METHOD NO./RE V. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER IIeid A 00-13/14 300066 6.5 RL 1.5 RL 33-1/3'f weld length was examined Vessel-to-Flange 11.5 RL from the seal surface (from the cen-terline of stud hole No. I to the centerline of stud holo No. 19).

1.3 Closure llead-to-Flange Uf 00-15/21 300080 OK$ 45T$ 45 $ 0 L 33-I/3~i of weld length was examined 60 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.

1.8 G-l Closure IIead Studs 00-1/22 300072 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 Examination performed to eeet Regulatory Guide 1.65 requirements.

Flattened thread on spare stud No. 45. See CHF 100331 (same as visual indication).

00-18/13 60

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 SwRI WELD INDI GATI0 NS E XAM I NATION EXAM.

SEC. XI SEC. XI ROCEDUR EXAM.SUM REMARKS AREA IDENTIFICATION METHOD ITEM N CATGY. NO.IREV. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER 1.8 G-l Closure llead Nuts VT 900-1/22 300079 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".

PT 200-1/22 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.

00-19/13 0,45 00 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 G-I Ligaments Between 00-5/15 300067 00 18 ligament areas were examined Threaded Stud Iloles (from the centerline of stud hole No. I to the centerline of stud hole No. 19).

1.10 G-l Large Closure Washers VT 900-1/22 300075 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 EXAtIINATION SUGARY TABLE REACTOR PRESSURE VESSEL AND CLOSURE HEAO (See Appendix A, Figure A-I) (Cont'd)

ASME ASME Svrnl MELO INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

ROCEOUR EXAM. SUAI REMARKS AREA IOENTIFICATION METHOD ITEMN CATOY. NO.IREV. SHEET NO. NO RECOROABI.E INSIGNIFICAN GEOMETRIC OTHER 1.10 G-I Small Closure Ilashers Vl'00-1/22 300077 Nashers Nos. 6 through 23 and spare washer No. 118 were examined.

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

1.13 I- 1 Closure Head Cladding 900-1/22 300081 Two 6" x 6" patches were examined.

200-1/22 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 EXAMINATION SIMIARY TABLE PRESSURIZER (See Appendix A, Figures A-2 and A-3)

AS'VIE ASME SwRI WELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXALI.

ROCEOUR EXAM.SUM REMARKS AREA IDENTIFICATION METHOD ITEM NO CATGY. NO.IREV. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER 2.1 POI-3 900-1/22 300049 X IS" of weld length were examined Upper Shell Course-to- 600-15/21 L,O N,45 T, (from 50" to 65")

Upper Head 54,604 2.2 Safety Nettle A 600-28/5 300039 4 RL Inside Radius Section 2.2 Surge Nettle 00-28/5 300005 4 RL Inside Radius Section 2.4 E-2 Heater Connections 00-1/22 300041 Examination performed to comply with Nos. 1 through 78 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.

2.6 G-2 Pressure-Retaining 00-1/22 300040 The first five bolts counterclock-Bolting wise, starting at the top of the Nanway Closure manway, were examined in place.

2.7 Vessel Support 900-1/22 300048 X 36" of weld length were examined Bottom Head-to-Skirt 600-15/21 L,45 T O'1,45 ,60 (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 ASM C SwRI WELD INDICATIONS EXAMINATION EXAM.

SEC. XI SEC. XI ROCEOUR EXAM. SUM REMARKS AREA IDENTIFICATION METHOD ITEMN ~WTGY. No.iREV. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOhIETRIC OTHER 3.2 Primary Inlet Nozzle 600-28/5 300083 39 RL Inside Radius Section Primary Outlet Nozzle 600-28/5 300082 39 RL No examination in the area of the Inside Radius Section support lug due to inaccessibility.

TURKEY POINT PLANT UNIT 4 1976 INSERV ICE NONDESTRUCTIVE EXAMINATION SIDINARY TABLE REGENERATIVE JIEAT EXCHANGER (See Appendix A, Figure A-S)

ASMC, ASME SwRI WELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

ROCEDUR EXAMl.SUhI REMARKS AREA IDENTIFICATION METHOD ITEhINO CATGY. NO./REV. SHEET NO, NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER 1ÃIEGRALLY WELDED SUPPORT SllSLL I 3.6 RGX (I)-Lug 900-1/22 300032 200-1/22 UT examination not feasible.

CLAHP RESTRAINT 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 EXAMINATION SIBIIIARY TABLE PIPING ASh'IE ASME SwRI WELD INDICATIONS SEC. XI EXAMINATION EXAM.

SEC. XI ROCEDUR EXAM.SUM REMARKS ITEAIN CATGY AREA IDENTIFICAT ON METHOD NO IREy SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHE REACTOR COOLANI'OP "A" p

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

4.1 RCC-(A)-4 900-1/22 300084 X L'lbow-to-Nozzle 200-1/22 X 600-3/26 0 L,O'II,45 T, No examination from the downstream Dev. IC2 45,60 side due to the nozzle configuration.

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

31" I.D.

4.1 F RCC- (A) -5 900-1/22 300085 Drilled hole. See CHF 100325.

Nozzle-to-Flbow 900-1/22 No recordable indications after cosmetic grinding.

PT 200-1/22 Drilled hole (same as visual indi-cation).

PT 200-1/22 No recordable indications after cosmetic grinding.

600-3/26 0 L,O NJ45 T, No examination from the upstrean Oev. Ifi2 45 ,60 side due to the nozzle configuration.

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

REACfOR COOLANT LOOP "B" See A endix A Fi ure A-7 29u I 0 4.1 RCC-(B)-4 VT 900-1/22 300084 Examination performed due to VT indi-Elbow-to-Nozzle cation on weld No. RCC-(A)-5, in order to comply with ASNE Section XI paragraph IS-244 requirements.

31'i I D 4.1 RCC- (B) -5 900-1/22 300085 Examination performed due to VT indi-Nozzle-to-Elbow 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 EXAMINATION SIDMARY TABLE PIPING (Cont'd)

ASIJE ASME SwRI WELD INDICATIONS E XAMINATION EXAIJ. ROCEDUR EXAM.SUM REMARKS SEC. XI SEC. XI AREA IDENTIFICATION METHOD ITEMN CATGY. NO /REy SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER 2" RTD IIOT LEG LOOP "A" See A endix A, Fi ure A-IS 4.6 K-2 7-PR-D VT 900-4/10 300020 Pipe Restraint 2" RTD COlA) I.EG LOOP "B" (See A endix A FiIIurc h-19)

K-2 15-PR-A-1 VT 900-4/10 300007 Pipe Restraint 4" PRESSURIZER SPRAY LOOP "B" See A cndix 4.6 K-2 9-PR-D2 VT 900-4/10 300008 Pipe Restraint 4.6 K-2 9-PR-El VT 900-4/10 300009 Pipe Restraint 4.6 K-2 14-PR-N VT 900-4/10 300021 Pipe Restraint

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

ASME ASM E SwRI WELD INDICATIONS EXAMINATION EXAM. REMARKS SEC. XI SEC. XI ROCEOUR EXAM.SUM AREA IDENTIFICATION METHOD NO.IREV. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER ITEM N CATGY.

4" PRESSURIZER SPRAY LOOP "C" Sce A endix A, Fi urc A-26 4.6 K-2 6-PS-B VT 900-4/10 300022 Pipe Support Structure 4.6 K-2 7B-PR-Ll VT 900-4/10 300010 Scale reading 2-3/4".

Pipe Restraint 4.6 K-2 12-PR-L4 VT 900-4/10 300011 Pipe Restraint 4.6 K-2 13-PR-LS VT 900-4/10 300012 Scale reading on mark No. 3.

Pipe Restraint 3" AND 4" PRESSURIZER RELIEF (See A endix A,

~Fi <<re A-22 4.6 8-PR-C VT 900-4/10 300030 Pipe Restraint

TURKEY POINT PLANf UNIT 4 1976 INSERYICE NONOESTRUCf IVE EXAMINATION

SUMMARY

TABLE PIPING (Cont'd)

ASSIE "ASME Swnl 'LVELO INOICATIONS EXAMINATION EXAM.

SEC, XI SEC. XI ROCEOUR EXAM. SUM REMARKS AREA IDENTIFICATION METHOD ITEM N CATGY. NO./REV. SHEFT NO. NO RECORDABLE IN S IG NI F I CAN GEOMETRIC OTHER 2" LETDOWN LINE LOOP "B" Sce A endix A, Fi ure A-42 4.6 K-2 12-PR-B 900-4/10 300019 Pipe Restraint 2" I.ETOOÃN LINL'O THREf: ORIFICES (See A cndix A, Fi ure A-43) 4.6 K-2 16C-PR-E 900-4/10 300026 Pipe Restraint 4.6 K-2 18-PS-C 900-4/10 300027 Pipe Support Structure 2" BORON INJECTIM LOOP "B" (See A endix A Fi urc A-33 4.6 K-2 7-PR-C 900-4/10 300013 Pipe Restraint 4.6 K-2 9-PR-F 900-4/10 300014 Pipe Restraint 4.6 K-2 13-PR-L 900-4/10 300015 Pipe Restraint 4.6 K-2 15-PR-N 900-4/10 300016 Pipe Restraint 2" BORON ItuECfION LOOP "C" (See A cndix A,

~Fi re A-54 4.6 K-2 11-PR-K 900-4/10 300017 Pipe Restraint

TURKEY POII<<FT PLAÃf IPiIIT 4 1976 INSERVICE NONDESTRUCTIVE EXAMINATION SIDDIARY TABLE PIPING (ContFd)

ASME ASME SwRI AFIELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

ROCEDUR EXAM. SUM REMARKS AREA IDENTIFICATION METHOD ITEMN CATGY. NO.IREV. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER 2" lllG)l llEAD SIS LOOP "B" AND CROSSOVER Sec A endix A, Fi ures A-37 and A-37a) 4.6 K-2 10-PR-P 900-4/10 30001B Pipe Restraint 3" CIIARGING I.INE LOOP "A" Scc A endix A

~F<< A-FF) 4.6 K-2 B-l'R-B 900-4/10 300054 Pipe Restraint 4.6 K-2 10-PR-E 900-4/10 300051 Pipe Restraint 4.6 K-2 14-PR-K 900-4/10 300052 Pipe Restraint 4.6 K-2 20-PR-0 900-4/1D 300053 Pipe Restraint 3" CIIARGING LINE LOOP "C" See A endix A

~F) <<rc A-CF) 4.6 K-2 13-PR-B 900-4/10 30005B Pipe Restraint 4.6 K-2 14-PR-E 900-4/10 300057 Pipe Restraint 4.6 K-2 23-PR-I 900-4/10 300056 Pipe Restraint 4.6 K-2 36-PR-Ll 900-4/10 300055 Pipe Restraint 4.6 K-2 37-PS-N 900-4/10 300023 Pipe Support Structure

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

ASME ASME SwRI IVELO I ND I GATI 0 NS EXAMINATION EXAM. ROCEDUR EXAhI. SUM REMARKS SEC. XI SEC. XI AREA IDENTIFICATION METHOD NO.IREV. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER IT Ehl N CATGY.

3" CIIARGING LINE TO VALVE 312C (See A en-dix A Fi ure A-411 4.6 K-2 7-PR-A VT 900-4/10 300059 Pipe Restraint

'-2 4.6 8'PR-0 VT 900-4/10 300060 Pipe Restraint 4.6 K-2 8-PR-F VT 900-4/10 300061 Pipe Restraint 4.6 K-2 8-PR-J VT 900-4/10 300062 Pipe Restraint 4.6 K-2 9-PR-L VT 900-4/10 300024 Pipe Restraint K-2 15-PR-R VT 900-4/10 300025 Pipe Restraint K-2 17-PR-T VT 900-4/10 300044 Pipe Restraint 4.6 K-2 21-PR-V VT 900-4/10 300045 Pipe Restraint 900-4/10 300046 "U" bolt missing from support.

4.6 K-2 21A-PR-N VT See CNF 100328.

Pipe Restraint Repaired by FPL.

VT 900-4/10 300038 Restraint disconnected from the Mall.

4.6 K-2 21A-PR-X Scc CNF 100327.

Pipe Restraint Repaired by FPL.

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

TURKEY POINT PLILVT UNIT 4 1976 INSERV ICE NONDESTRUCTIVE EXAIFIINATIOef S(BS4ARY TABLE PIPING (Cont'd)

AS4ME ASME SwRI WELD INDICATIONS SEC. XI SEC. XI EXAMINATION EXAM.

ROCEOUR EXAM. SUM ITEMN CATGY. AREA IDENTIFICATION METHOD REMARKS NOJREV. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER 2" SEAL INJECTIOel LOOP "A" (See A endix A,

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

~ri re *-44)

K-2 31-PR-L 900-4/10 300036 Pipe Restraint 4.6 K-2 37-PR-0 900-4/10 300037 Pipe Restraint

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

ASME ASh'IE SwRI WELD INDICATIONS SEC. XI SEC. XI EXAMINATION E XAAI.

ROCEDUR EXAM. SUM REMARKS AREA IDENTIFICATION METHOD ITEM NQ CATGY. NO./RE V. SHEET NO. NO RECORDABLE INSIGNIFICAN GEOMETRIC OTHER PUMP A 5.5 G-2 Seal Housing Bolting 900-1/22 300042 The bolting was examined in place.

4 Studs and 8 Huts 5.6 K-1 Pump Support sl VT 900-1/22 300050 X Ho examination from 38" to 63" due PT 200-1/22 X to support configuration.

UT Ho available technique for UT examination.

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

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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

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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 II between 20 and 50 percent of DAC III while others were above 50 percent of II I DAC, both of the preceding state- III I'I ments were recorded. 'III

/

g J I

1. Reactor Pressure Vessel +I I I II,S4

a. Reactor Pressure Vessel-to-Flan e / I Circumferential Weld. The Reactor Pressure I S4 Vessel-to-Flange Circumferential Weld (Weld A) I was examined ultrasonically from the flange I I

I.S4 seal surface. A module containing three trans- I I ducers, mounted such that 1.5-, 6.5-, and I I

Fl.ANGE 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- REACTOR PRESSURE formed during the examination. The angles and VESSEL 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 FIGURE 2. BEAM PATHS USED TO No. 1 to centerline of stud hole No. 19) in EXAMINE THE REACTOR PRESSURE accordance with the requirements of the ASME VESSEL-TO-FLANGE WELD Section XI. Calibration standard was used to calibrate for this No.'-CSCL-1-TKY SCARCN UNIT NOOVL S examination.

b. Reactor Pressure Vessel Closure 4 LONO Head-to-Flange Circum erential Weld. The WSLO Q Reactor Pressure Vessel Closure Head-to-Flange 40+ SNSSR 4S+ SeCJR Weld was examined ultrasonically from the head shell outside surface (see Figure 3)., This WSLO SCAN WLLO g 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 FIGURE 3. BEAM PATHS USED TO standard No. 7-CSCL-39-SLC was used to calibrate EXAMINE THE CLOSURE for this examination. 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.

d. Reactor Pressure Vessel Closure Head Nuts. Visual, manual liqui penetrant (as required (y 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.

A P-number comparison between the nuts FIGURE 4. CONCEPTUAL and the UT calibration standard used is not possible DRAWINGS SHOWING because the nut material is not listed in the EXAMINATION OF RPV CLOSURE P-Number Classification in ASME Section IX. However, HEAD NUT AND CLOSURE HEAD STUD it was quite apparent to the experienced Level II 25

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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 Seal Surlace SEARCH UNIT Search Unit 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

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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 0-deg longitudinal wave and 45- and 60-deg shear wave search units. 'tilizing 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) 2-in. Remote Thermal Detector Loop "B" Cold Leg (3) 4-in. Pressurizer Spray Loop "B" (4) 4-in. Pressurizer Spray Loop "C" (5) 3-in. and 4-in. Pressurizer Relief (6) 2-in. Boron Injection Loop "B" (7) 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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~i