ML17216A510

Inservice Insp Rept for 851020-1224.Listed Components Inspected & NDE Techniques & Results Discussed.Statement Re Status of Work for Current Interval Encl

ML17216A510
Person / Time
Site:	Saint Lucie
Issue date:	04/25/1986
From:	LIALLO C A, UVABA J E ARKWRIGHT BOSTON MANUFACTURER'S MUTUAL INSURANCE, FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17216A509	List: ML17216A508 ML17216A510
References
NUDOCS 8605050121
Download: ML17216A510 (59)

Text

FORM NIS-1 OWNERS'ATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules page 1 of 14 1.Owner Florida Power and Liciht Co.9250 W.PlaqPler Miami Fla.(Name and address of Owner)2.Plant St.Lncie Plant P.O.Box~128 Ft.Pierce Fl 33454 (Name and address of Plant)3.Plant Unit 1 4.Owner Certificate of Authorization (if required)N/A 5.Commercial service date 21 December 1976 6.National Board Number for Unit~N A 7.Components Inspected Component or Appurtenance RPV VESSEL PRESSURIZER STM.GEN.A&B REACTOR COOLANT Manufacturer or Installer Combustion Eng.Combustion Eng.Combustion Eng.Ebasco Manufacturer or Installer Serial No.N A N/A N/A 2"-RC-142 State or Province Number N/A N/A N/A N A National Board Number N/A N/A N/A N A SAFETY INJECTION Ebasco 6"-SI-112 6"-SI-113 12"-SI-477 10"-SI-420 10"-SI-422 6"-SI-409 6"-SI-462 N A N A CVCS MAIN STEAM FEEDWATER Ebasco Ebasco Ebasco 2"-CH-148 34"-MS-28 34"-MS-29 20"-BF-19 18"-BF-51 N/A N A N/A N/A.N A N A Note: Supplemental sheets in form of lists, sketches, or drawings may be used provided (1)size is 8 1/2 in.x ll in., (2)information in items 1 through 6 on this data report is included on each sheet, and (3)each sheet is numbered and the number of sheets is recorded at the top of this form.8&080g012i 05000gS 8s04~0 PDR ADO'~PDR 6

'7 1 NIS-1 REPORT CONTINUED page 2 of 14 8.Examination Dates 10-20-85 to 12-24-85 I 9.Inspection Interval from 6 2/3 Irs.to 10~ears Interval Dates 12-21-76 to 2-11-88 10.Abstract of Examination.

Include a list of examinations and a statement concerning status of work required for current interval.GENERAL The Inservice Examinations (ISI)of.selected Class I,II components of Florida Power and Light Company's (FPL)St.Lucie PLANT (PSL), UNIT NO.1 , was performed during the refueling outage which began on 20 October 1985.These examinations constitute the SECOND OUTAGE of the THRID 40-MONTH PERIOD OF of the First Inservice Inspection Interval of COMMERCIAL OPERATION.

FPL requested and was granted extension of the first Inspection Interval.(See item 9 above for new interval dates)s The components were selected in accordance with LONG-TERM PLAN which was prepared to meet the requirements of SECTION XI of the AMERICAN SOCIETY of MECHANICAL ENGINEERS BOILER and PRESSURE VESSEL CODE," RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS," 1974 EDITION with ADDENDA through Summer 1975.The following Nondestructive examination techniques were used in the'performance of the Inservice Inspection Examination activity.VISUAL EXAMINATIONS Visual examinations on class 1 and 2 component supports and valve bolting was conducted by St.Lucie construction organization utilizing qualified and approved NDE examination procedures.

EDDY CURRENT EXAMINATIONS During the refueling outage Eddy Current inspections were conducted from ll November 1985 to 2 December 1985 on Steam Generator's" A" and"B".These examinations were conducted by FPL.8,166 tubes were examined on Steam Generator" A", and 8,214 tubes were examined on Steam Generator" B".See attached NIS-BB report for summary of examination results.SNUBBER EXAMINATIONS AND TESTS Snubber visual examinations and functional testing was conducted in accordance with the requirements of PSL-1 Plant Technical Specifications 4.7.10.These examinations and testing were conducted by Paul-Munroe Energy.Services.

NIS-1 REPORT CONTINUED page 3 of 14 INSTRUMENTED INSPECTION TECHNIQUE Instrumented Inspection Technique was implemented during this outage by H.A.F.A.International under the Topical Report 135(P)(A), titled"Instrumented Inspection Technique as an Alternate to the Hydrostatic testing requirements for ASME Class 1, 2 and 3 systems and components".

FPL requested and was granted approval to use this alternative testing technique as permitted by 10 CFR 50.55a (a)(3), by NRC letter dated 8 November 1985 under NRC TAC No.59917.The VT-2 (Visual)examinations was conducted in conjunction with the IIT technique in accordance with the requirements of Section XI, with the exception of the four (4)hour hold time which was redused to two (2)hours as approved by NRC.NOTE: The Authorized Nuclear Inservice Inspector has taken exception to this technique as meeting the requirements of Section XI.FEEDWATER FOLLOWUP EXAMINATIONS FPL also conducted volumetric examinations of the Feedwater Nozzle's.A 100%manual Ultrasonic examination was conducted from the nozzle ramp out to a point of one (1)pipe diameter on the elbow side.SYSTEM PRESSURE TESTS The system leakage tests and visual (VT-2)examinations of class I systems prior to plant startup was performed by the plant during reactor*coolant system overpressure test.CORE BARREL FOLLOWUP EXAMINATIONS Followup examinations of the core barrel was conducted during this outage by Combustion Engineering.

These examinations included a remote visual of the repaired areas to look for evidence of looseness, motion, or wear'on the plugs and patches as well as indications of new or continued crack growth in the base metal.ll.Abstract of Conditions Noted.VISUAL EXAMINATIONS The visual examinations of component supports identified Two (2)pipe supports that shifted position during operation, and loose parts.The visual examinations of valve bolting was conducted.inplace and identified conditions being boric acid accumulation and evidence of leakage~.

NIS-1 REPORT CONTINUED.page 4 of 14 EDDY CURRENT INSPECTION The Eddy Current examination results conducted during this outage are as follows: on Steam Generator" A" , 263 tubes had indications between the range of 20%to 39%, and 48 indications were noted between the 40%to 100%range.On Steam Generator" B", 109 indications were noted between the 20%to 39%range and 20 indications were noted between 40%to 100%range.SNUBBER EXAMINATIONS AND TESTS During the visual inspections two (2)generic and several specific deficiencies were discovered.

Spherical bearings were found to be loose or displaced.

These were considered a generic problem as identified in IGE Circular 81-05"Self Aligning Rod End Bushings".

Several other snubbers were found to have oversized load pin hole in the pipe clamp or beam attachment.

The hole size mismatch was due to a design error.Other deficiencies that were discovered were due to errors during installation and maintenance conditions.

The limited operability test revealed some snubbers which were frozen or incapable of free movement over their full range of travel.Nine (9)of the failures resulted from the snubber having been overloaded while inservice.

During the functional testing several snubbers bacame frozen during or after the load test portion of the tests.Six (6)ITT Grinnell snubbers failed the functional test.Two (2)snubbers failed on lockup velocity criteria due to clogged constant bleed bypass orifice'n their control valves.Two (2)needed slight adjustment and two (2)had to be replaced due to internal damage.Four (4)Pacific Scientific mechanical snubbers failed to achieve the manufacturer's activation criteria of 0.02 g.The failures were all due to dirty capstans/capstan springs.NOTE: Included within this report are summary tables of snubber anomalies requiring corrective action.INSTRUMENTED INSPECTION TECHNIQUE Instrumented Inspection Technique was conducted on the Charging system, the letdown system and the safety injection system.The results of these examinations and tests are on file at the site.TEST NO 1 IPT 02 SAFETY IN JECTION LOOP 1Al g lA2 g lBl i AND 1B2 1-IPT-04 CVCS, LETDOWN LINE 1-IPT-05 CVCS, CHARGING LINES 1-IPT-06 CVCS, CHARGING LINE NIS-1 REPORT CONTINUED page 5 of 14 FEEDWATER AUGMENTED EXAMINATIONS NO reportable indications were noted during the conduct of the ultrasonic examinations.

Several Geometric indication were recorded and determined to be due to root geometry.CLASS I SYSTEM LEAKAGE TESTS Evidence of minor leakage was noted at some valve packing glands and at bolted connections.

The amount of leakage was determined to be acceptable

.CORE BARREL FOLLOWUP EXAMINATIONS The results of the visual examinations showed no crack extension and no evidence of plug or patch movement.During the visual'xamination on lug no.8 a Burr was noted at the bottom of the Core Support Barrel lug.12.Abstract of Corrective Measures Recommended and Taken.GENERAL INFORMATION The results of manual UT examinations were recorded on the applicable indication report sheets as specified in the appropriate NDE procedure.

The information documented on these forms describes the parameters associated with those indications which were greater than the recording levels specified in the applicable NDE procedures.

When required, the location and nature of reflectors were determined by analyzing the indications parameters recorded on the forms described above.The analysis is documented on a resolution sheet, which are included as part of the data package.In the performance of the UT examinations, the data recording level was established by the applicable NDE procedure.

Visual examinations record sheets were used to record the results of those examinations.

The equipment and/or materials used in the visual examinations are also identified on the data sheets.The summary table, which are included as part of this report, provides information and results for the nondestructive examinations that were conducted during this Inservice Inspection activity.Specific information and documentation of these examinations are on file at the St.Lucie Plant document control section.5 NIS-1 REPORT CONTINUED page 6 of,l4 FEEDWATER AUGMENTED EXAMINATIONS Geometric indications were verified against the previous examination records and no corrective action was required.VISUAL EXAMINATION The two pipe supports that shifted during operation were adjusted as required to meet the design criteria.EDDY CURRENT EXAMINATIONS Forty six (46)tubes were plugged on steam generator" A" and nineteen (19)tubes were plugged on steam generator" B".SNUBBER EXAMINATIONS AND TESTS PC/M 172-185 was issued to correct both'the spherical bearings and the oversized attachment holes.The PC/M included the recommendations of IGE Circular 81-05 to correct the spherical bearings.A bushing was inserted in the larger hole to correct the slack in the oversized attachment holes.Snubbers identified as having been subjected to service-induced overload were upgraded to a larger capacity.The.problem with the PSA 0.25, 250 lb.load snubbers was corrected by replacing them with PSA 0.25, 350 lb.load snubbers.The snubber by the leaking valve was replaced and the leaking valve was repaired.All defective snubbers were either repaired or replaced and/or modified.SYSTEM PRESSURE TESTS All leaks identified during the system hydrostatic-and instrumented inspection technique were evaluated, dispositioned and corrected in accordance with Plant procedures.

Documentation data packages or on file at the site.-CORE BARREL The burr at the bottom of lug no.8 was removed and determined to be acceptable.

Examination data was compaired against the baseline data and determined to be acceptable for continued service.

4 Nls-1 REPORT CONTINUED page 7 of 14 We certify that the statements made in this report are correct and, the examinations and corrective measures taken confor'm to the rules of the ASME Code,Section XI.Date: 4-25-86 Signed FLORIDA POWER&LIGHT CO.By Owner Certificate of Authorization no.(if applicable)

~N A Expiration date N/A CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and/or the State or Province of OHIO and employed by*of NORWOOD NRSS have inspected the components described in this Owners'ata Report during the period 20 Oct 1985 to 24 Dec 1985 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owners'ata Report in accordance with the requirements of the ASME Code,Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinati:ons and corrective measures described in this Owners'ata Report.Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.

Date: 4-25-86 Inspector's Signature FACTORY MUTUAL SYSTEM Commissions NB-7719 National Board, state, Province and No.*ARKWRIGHT BOSTON MFG'S MUTUAL INSURANCE COMPANY I 1 r 0 NIS-1 REPORT CONTINUED SUPPLEMENTAL SHEET NIS-1 page 8 of 14 l.Owner: Florida Power&Light Co.9250 West Flagler Miami, Florida 33152 2.Plant: St.Lucie Nuclear Power Plant P.O.Box 128 Ft.Pierce, Florida 33454 3.Plant Unit".1 4.Owner Certificate of Authorization

N/A 5.Commercial Service Date: 21 December 1976 6.National Board Number for Unit: N/A 10.REPORT NUMBER ORGANIZATION DESCRIPTION OF SERVICE MCI-PSL-85-100-1 NO NUMBER ASSIGNED CEN-326 (F)1-IPT-02 1-IPT-04 1-IPT-05 1-IPT-06 FPL FPL CE FPL INSERVICE INSPECTION FINAL REPORT OF AUGMENTED, ISI ON FEEDWATER PIPING EDDY CURRENT EXAMINATION OF STEAM GENERATORS FINAL CORE SUPPORT BARREL INSPECTION REPORT POST CYCLE SIX TEST DOCUMENTATION ON (IIT)INSTRUMENTED INSPECTION TECHNIQUE

FORM NIS.-BB OWNERS I DATA REPORT FOR EDDY CURRENT EXAMINATION RESULTS As required by the provisions of the ASME CODE RULES PAGE 9 OF 14 EDDY CURRENT EXAMINATION RESULTS PLANT: St.Lucie Unit No.1 EXAMINATION DATES: ll November 1985 THRU 2 December 1985 STEAM GENERATOR NUMBER S/G II A S/G II B II TOTAL TUBES INSPECTED 8166 8214 TOTAL INDICATIONS 20%N/A N/A TOTAL INDICATION OR=TO 20%TO 39%263-109 TOTAL INDICATION OR=TO 40%-100%48 20 TOTAL TUBES PLUGGED 46 19 LOCATION OF INDICATIONS STEAM GENERATOR G II All S/G IIB II BATWINGS NONE FULL EGGCRATES 1 THRU 8 54 22 PARTIAL EGGCRATES 9 AND 10 47 14 TOP OF TUBE SHEETTO 1 DRILLED SUPPORT 211 93 CERTIFICATION OF RECORD We certify that the statements in this record are correct and the tubes inspected were tested in accordance with the requirements of St.Lucie Plant Technical Specifications.

FLORIDA POWER&LIGHT COMPANY (Organization

)DATE 4-25-86 BY FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As required by the'provisions of the ASME Code Section XI 1.Owner: name FLORIDA POWER&LIGHT CO.address P.O.BOX 529100 MIAMI'LORIDA 33152 2.Plant: name ST.LUCIE NUCLEAR PLANT address P.O.BOX 128 FT.PIERCE, FL 33454 3.Work Performed by: name PAUL MUNROE address 1701 W.SEQUOIA AVE P.O.BOX 5900 ORANGE, CALIFORNIA 92668 Date 4-25-86 sheet 10 of 14 Unit 1 PC/M NO.180-185 repair organization P.O.No.job No., etc.Type Code Symbol Stamp N/A Authorization no.N/A Expiration Date N/A 4.Identification of system: STEAM GENERATOR AND REACTOR COOLANT PUMP SNUBBER'S 5.(a)Applicable Construction Code N/A CASE NO.N/A (b)Applicable Edition of Section XI utilized for repairs or replacements 1974 EDITION THROUGH THE SUMMER 1975 ADDENDA 6.Identification of components repaired or replaced and replacement components Name of Component Name of Mfr.Mfrs.Ser.Nat'1 No.Bd.No.Crn No.Other Year Ident-Built ifica-tion Repaired Replaced or repl-acement ASME Code stamped (yes,no)STM.GEN SNUBBER ITT GR INNEL MODEL NO.BH-1224 N/A N/A N/A N/A 1=002 N/A 1-001 N/A MODIF-IED MODIF-IED YES YES REACTOR COOLANT PUMP N/A N/A N/A N/A 1-017 1-018 1-019 1-.020 N/A N/A MODIF-IED REPLA-CED YES YES 10 NIS-2 REPORT CONTINUED PAGE 11 OF 14 7.Description of work: PERMANENTLY DELETE THE ALLEN SCREW RESTR ICTION OR IFICES IN THE ITT SNUBBER VALVE.REPLACE TWO (2)SNUBBERS DUE TO INTERNAL DAMAGE.8.Tests Conducted:

Hydrostatic Pneumatic Nominal Operating Pressure Other X Pressure psig Test Temp.F MINUTE HOLD TIME 9.Remarks: Applicable Manufacturer's data Report's are attached NONE CERTIFICATE OF COMPLIANCE To certify that the statements made in this report are.correct and this REPLACEMENT conforms to Section XI of the ASME Code.(Repair or Replacement

)Signed FLORIDA POWER&LIGHT CO.BY (Owner or Owner's Designee)(Title)4-2'-8 (-a-C((Dhte)CERTIFICATE OF INSPECTION', the Undersigned, holding a valid commission issued by the'ational Board of Boiler and Pressure Vessel Inspectors and the State or Province of OHIO employed by***of NORWOOD, MASS have inspected the REPLACEMENT described in this report on 25 APRIL 1986 and state that to the best of my knowledge and belief, this REPLACEMENT/MODIFICATION has been constructed in accordance with Section XI of the ASME Code.By signing this certificate, neither the Inspector nor his employer takes any warranty.expressed or implied, concerning the replacement described in this report.Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspe tion.Date 4-25-86 (Inspector)

Commissions FACTORY MUTUAL SYSTEM COMM.NO NB-7719 (State or Province, National Board)***ARKWRIGHT BOSTON MFG'S MUTUAL INSURANCE COMPANY NIS-2 SUPPLEMENTAL SHEET PAGE 12 OF 14 l.OWNER: 2.PLANT: FLORIDA POWER&LIGHT P.O.BOX 529100 MIAMI, FLORIDA 33152 ST.LUCIE NUCLEAR PLANT P.0.BOX 128 FT.PIERCE, FLORIDA 33454 DATE: UNIT: 1 4-25-86 3.WORK PER FORMED BY: PAUL MUNROE UNDER THE DXRECTION OF FPL JOB NO.PCM 180-185 4.IDENTIFICATION OF SYSTEM: 7.DESCRIPTION OF WORK: STEAM GENERATOR 6 REACTOR COOLANT PUMP ITT GRINNELL FIGURE 20 0 g 5 STROKE HYDRAULXC PXSTON CYUNERS WITH MODEL BH-1224 DUAL ORIFICE TYPE LOCK UP VALVES PAUL MUNROE, UNDER THE DIRECTION OF FPL DISASSEMBLED THE LOCK UP VALVES TO DETERMINE THE CAUSE OF FAILURE.NOTE: CAUSE OF FAILURE, MINUTE DEBRIS WHICH COMPLETELY BLOCKED THE BLEED VALVE ALLEN SCREW ORIFICE.A.DISASSEMBLE SNUBBER BLOCK VALVE PER PHD-6511-6.

B.DRILL OUT VALVE ORIFICE C.REASSEMBLE VALVE PER PHD-6511-6 D.ADJUST BLEED RATE AND LOCK UP RATE E.FUNCTIONAL TEST (LOCK UP 6 BLEED RATE)F.RETURN.TO SERVICE ITT AFFECTED SNUBBERS: NAME OF COMPONENT FPL TAG NO.MARK NO.REPAIR/REPLACE OR MODIFICATION STEAM GENERATOR REACTOR COOLANT PUMP 1-001 1-002 1-017 1-018 1-019 1-020 SS-1 1A SS-2 1A lAl 1A2 1Bl 1B2 MODIFIED MODIFIED MODIFIED MODIFXED REPLACED REPLACED 12 NIS-2 SUPPLEMENTAL SHEET PAGE 13 OF 14 1.OWNER: FLORIDA POWER&LIGHT COMPANY P.O.BOX 529100 MIAMI, FLORIDA 33152 2.PLANT: ST.LUCIE NUCLEAR PLANT P.O.BOX 128 FT.PIERCE, FLORIDA, 33454 DATE: UNIT: 1 4-25-86 3.WORK PAUL MUNROE PER FORMED BY: JOB NO.172-185 4.IDENTIFICATION MECHANICAL SNUBBER END ATTACHMENT WITH OF SYSTEM: SPACER AND BUSHING PROBLEMS 7.DESCRIPTION OF WORK: PROVIDE MECHANISM TO ELIMINATE THE EXCESSIVE CLEARENCE BETWEEN THE PINHOLE OF PIPE CLAMPS/END BRACKETS AND THE SNUBBER PINS.THIS MECHANISM WILL ALSO ELIMINATE THE EXCESSIVE GAPS BETWEEN THE PIPE CLAMP HALVES AND THE ROD END BUSHINGS.SNUBBERS AFFECTED BY THIS MODIFICATION:

MANUFACTURER PACIFIC SCIENTIFIC TYPE PSA-3 PSA-3 PSA-10 PSA-10 PSA-3 PSA-3 PSA-10 PSA-10 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-3 PSA-0.25 PSA-0.25 PSA-1 PSA-0.25 PSA-0.25 PSA-3 LINE NO.RC-005-34A RC-005-34B RC-005-12A RC-005-55C"RC-005-62A RC-005-90 BF-661-407 BF-661-407 SI-968-1205 SI-969-6193 SI-969-6195 SI-973-, 240 CC-1899-48 CH-64-40 RC-5-475 CH-129-99 RC-1-124A CH-142-18 CH-141-44A CC-1899-2200 FPL TAG 1-021 1-022 1-024 1-028 1-029 1-031 1-048 1-049 1-055 1-059 1-060 1-074 1-097 1-106 1-121 , 1-122 1-148 1-160 1-191 1-202 13 St.Lode Unit~$hssrvtce Irxeecttm-Oct

-Dec)965 Seemly of Sca4ber Anoeaoltss Requtrlng Corrects AcQae Toy trek Nurnhcr the)hr lml~SS-1 IA SS-2 IA HC5~1A l~S&4 IA l~S&4)A I~S&4 IA 1~SS-7 IA-I~~IA HXS SS"I I8 1&10 SS 2 IB 1&11~IB mQ~IB Ma~IB 1%14~IB I<%SS-7 IB M16~IB 1&17~)A'I Hl" IA2 148<t51'OO~'182 HQI'C~54L 14RCW&64

~~RC~I2A 1~~jC~~~'RC~mea S-ml JaCW~O m-200'TT-200.00 ITT-20030 AT-20080 Ili-200'T-200'TI-200AXI ITT-200AN iiT-200AM AT-200 IlT-20040 ITT-200'ii-200AM N-200'TT-200AM

-AT-200'Tf~.00 AT~.OO ITT~.OO m'~.00 PSArB.OO PSALM AO PSA-10.00 PSA-IOAO PSA-MN PSA-3'A SL NA Nk Nk NA NA NA NA NA, HA NA, NA NA NA Nk IIA NA, Qkerlcslbe~gdtslodped-

~ericelbsa Ing<%smudged.

QQrhtlbarhg 4sio49ed.Syae Iceitea hgs~dtsytac d.Qkaricelbearh94siodyed-Shrlcelbeehe dtslodged.

H/A N/A H/A H/A N/A-HtA N/A N/A N/A N/A N/A N/A N/A N/h N/A N/A N/A N/A N/A 8/A N/A N/A N/h N/A N/h N/A Fwctionel Test Aeeeltes Control Valve Control Vahe Control Vahe Control Vahe Gets Valve Control Valve C trolVahe Control Vahe Control'Valve Control Vahe Controt Valve Cm~l V~Contr>A Valve Controi VAe Control Vatve Consol Valve (>gay 5 Aalease Aeteese rate Ngh 4rag faQure~dra9 fatIMre N/A H/h I/A N/A Hlh&eeeaat AQg Rsyatrad Qspatred Qopatrad Aspsrfred Act&red Qeyafred Rope)red Repsdred Qepatrad ihydred Royal')Repaired QeyaIra0 Repaired Aepatrad QeyaW4 h+eted fustad AepIaced Qeytacad Aspatrod Aeyatrad Aepatrad Ibpeirad Aeyetrad Rsplacad R.Lode Unit~i kesrvk>>lnspecUm-Oet.-Dac..1985 SLarxnary of Sekbsr Anosnslkes AequHng Ox receive Ac%as t&44Hi M34$~~$07&5164 l~ff&64M14 1~~%~1~?1~8&461~l~Sl~8"1205't~SMQM195 SMRH5$95 1~S1~12'70 8&971~M?4'l~240 l~SWATS-)27 l~?.CC-1%&4)HO'1 0C-l?-l 1-106 CH~O 1-11?AC-1 221 A 1-1 18 RC-1-1M'-120 RC-1-192A 1-121-Sr&4?S 1-122 CH-l~1-123 RC-21?%1-'l24-OHiSfi4C 1-DS CH-M&9 1-126 CH-14bRC 1-12?AC<'l&9A P Jfri55AO PSA-35'SA&.00 PJJ!@%ATE PSA-10.00 PSA-10.00 PSA-3.00~AS PSA&.00 PSA-10.00 PSAri5AO PSALM PSA-10.00 PSALM PSA-T0.00 PSALM AO PSH)28~2S PSA2S~25~25 PSA2S~25 PSA&2S PSAr02S PSA&25 Qanp~hg.Chep sgechg.Sphsrlcalbearhg crade0 Pip>>dssnp bonny hase.-'~icNbearh94sWgad S14erkal bearhg dislodged Spterlcalb>>arlog 4sihxlg>>4 Sgarlcal boa4g 4smodged Sgbsrkal 0>>arhydhlodgad.

Oat on eAbsr body NA Qjbarkalbaarhg d}slodgsd.

PaNe hhd: T ahelW~C.Spb>>rlcalberhg east&ed.NA Sph<<kal herby Os)+led.HA NA NA Over,shed hob 1n damp.Overahsd bola hc}cap.NA NA Nh Nh HA N/A H/h l4/h Nfh Nfh N/h tl/A 8/A l4/h Il/A Ssvbbar N/A NIA N/A N/A 8/A NIA Nfh N/A N/A N/A N/A N/A N/h N/h H/A%'h N/h N/A N/A H/A H/A H/h Lin@e4sh4e 14/A Beetled AQg H/h&ceeded.02g FaQ>>d to odheta N/h~drag fallow Ngh drag falter>>Ngh drag Mare 8/h N/h Ngh 4 ag Mora Ngb~false H drag ftQura Lockedrag>

lo test Ngh~faSF>>hddad spaoes.Added W~es.Asp air>>d f4gekad Aepalrad Repaired A>pair>>d Aep>>Wd RgeW4'fbylacad Aplacwl lbgHacad Asp aired Asplaced Qepla cad Qgehwl Qeplacad Qeplac>>d Replaced hddedbu&lng AddedhusNg Qeplaced A<placed Replaced Rsgaced Replaael

~~

St.Ludo Unit+1 b3sendce IeeeNon-Od.-Doe HBS Surgery of Qxkber AnamaNes Qequlrbg CetneUve Actus 1-QS~ttQ-~I-'l20 2&3A 1-129'L-1-$24: l-)30 ttQ-~1-131.tSI-15-3A 1-U2 CH-1ÃrXi6 1-7Xf tSf-14-3A 7-134 CH-1~9 1-137.CH-)2%459 1-Q8 AC-114-129 1-139 AC-221-i62 1-140 CH-lN~1-141-CH-145-26C l-l4 CS-141-74 1-14l PŽM1 1-14'RC-18&8 1-'l4$.CH-14'-145 AC-1-25C 1-MIRAC-1-%@A, 1-149 1-150 l%H34A 1-151.CH-142-17 1-)S4~fSl-l~l-1SS'C-1~9 1-155 XQ-1244 1-157 QC-21+45 PSAr025 PSA26 PSH725 PSAO25~25 PSA&28 PSA&25~2S RA<)2S PSA25 PSH)25 PS'$~25 P8k025 PSk425 PSA25 PSA2S PSA25 PSA-lAN PSA-1AO PSA25 PS~BS PSM)25 PSA2S PSA-02S PS&425 Nh NA NA Nh Nh , NA NA Hk NA NA Nh HA-Q-Nh Nh NA HA NA Sbberkalbeahg dIQodyed.Nh r NA NA NA NA NA NA Opeak@ity Test Axealles NIA N/A Snabfheea NfA NIA Sabtwr f ceca.H/A N/A S04bN'l'own.

N/A NIA N/A NIA N/A Qekbe thesn.NIA NIA Umnlted~NfA NfA NIA NIA H/A NfA N/A UmttN strobe fuoctio&Test hnwno5es~dray fa9ure Ngh dray faQre High dray faire High 4ray fabbro drag failure Ngh drag faire~dray faire~4ray faNre Ngh drag Mhre~dray fable High dray f thre High 4ray falkre Ngh drag ASKS Nfh locke}~ln test~drayf ere NA'/A~dray faSre~4ray faH~Ngh 4ray false ggh dray fafkre ,~drayfahre

~dray ANure 8/A emtua 1 hsorvlce tnsyectlon-Oct.-Dec 198S Selaery oS Sefhar hnomo5sa Raquirloy Corrective Actus OpanhQfty Test hnctiael Test A noae@os Aaomo?bs 1-158 CH-1~'l6 1-160'>F18 l-l61'C-165-11 162 AG-217%1-163 SM~)1-164 Sl~1-16?Of67&1 AC-1 14-)2$1-169.$C~26 1-17 l AC-218-26 1-G2 AC~11 1-1TS" OH%41 1-176 N-F41 l-)77 QC-22~1-176 ttS&H41 1-)60-AC-220-114 M82 AC-219%A)-105" OSSA 1-186-8-l~1-167%94)1-1$8" AC-1QHP l-189 Q~iO 1-190, CH-Nl~1-191~CH 111~1-194-fly-75 1-195~N%-200-250

~e, (Pagel P8k425 PSH?2S P8lr025 PSA25~25 PS%425 PSA&2S PSAO2$PSH325 PSA&25 PSA&25 PS&)25 PSA&2S PSA2S PSAr025 PSA&2S PSA-1 AN PSA25 PSA-025~2S PSA&2$PSA2S~25 PSA25~2$NA erskned Me 4c~.--NA NA NA NA NA Nh Nh NA NA HA HA, NA NA PadClesNiAy.

NA NA NA NA NA Heeiy coreoelonmheelny.

NA Ieerlng4shdgad; muke5 hrekei.NA NA Nfh N/A Stabber theat Unde stroke Nfh N/h N/A Nfh N/A N/A N/h Nfh N/A N/A 8/A N/A 8/A tlmttei~Sekha sheen.Nfh NIA'/A NIA N/A Snye'aten.

8/A Ngh drag f8~H/A KIA Ngh dray Cdlee Ngb drag Whee Ngh dray faStre Ngh dray Mure Ngh drag failure Ngb drag faSre Ngh dray f Huee Ngh dray faire~drag f Ore Igh drag 5d~Sgh drag f4~Sgh drag fibre N/A Syhdray Qthre Ngh drag M~NIA egh dray retire Sgb drag feQre~drayr~Ngh Oreg false N/A Ngh drag falhre Replaced Repleced Qpgrahs PSA-1 Asplaaed Qsp1aced Asg Baaed Replaced A~laced Itiplaced ihg&cod Replace QIptaced Aephced Aephced Qsptaced@gested Aaplaaed Replaced St.Lode Unit J heorvlce iaseec5on-CcL,-Qec)985 Scenery of Satb+'AgaN5e Qequfrhg Cartvct4e A@Dam Tag Nark NNnba Neer OpsrehBRy Test Aamo5es 1-196.'%H-7A 1-198 N%-200-29 1-199 QW?8-16 1-200 C&478-1930 1-201 Qr4?8-2'A5 1-202~-a~2200 5-204 BF4$%9010 1-215 N~9-284 1-217 i&I~1 1-218 3~01 1-219 CH-25~9 1-220 CH-2ZHf10 1-RQ AC-1&F1 1-225 RC-24Rll 1-22?RC-24&44 1-228~lfC-247%1-2294IC<4?~

1-2304RC-24?~

1-231"f RCSV-l3 1-234 ACSV-22)-255: RC6V-25 1-236 7S>>Oia 1-FJ?Sl"101-13 1-240'P!W57

~~25 PSAr025 PSA-1 AS PSA-\.00 PSA-5AS PSA-5.00 SP-30.00 IP-70AS PSA2S~)2$pSH)25~50 PSA&50 PQIr450 PS'5 PSH)25 PSH)25 PSA25 PSA<2S PS&426 PSk425~25~25~.00 NA hnp~r type ioed ph.NA Bearing cbaraae NA Sg4arlcalbearh94slodged.

Paddle/dsrnp eatect.~.Paddle/cleep cwhct.mao.NA NA NA NA NA'A NA Ape chmp bose.Pfpe clamp loose.Padde beat, ln centmtwlO dev}s.NA Loed Cef leyreplily haMed.NA Nh NA NA Rubber frmea.N/A Nlh N/A N/A N/A N/A SNNxI'thm.

Snubber frozen.Snnkber Orozco.Sacker Oetn.Offtlcult to~.Free 4rhg stroke Froze durity stretto St&be lb'.N/A N/h SxQwr Oaten.N/A 8/h N/A~~faLhre N/A N/A~drag ANre N/A Ngh drag faQF0 N/A M/A Ngb~faBee Ngh drag~N/A N/A~drag~il/A N/A N/A N/h Ngb drag faire NlA~Nag A%re Exceeded AQy Aspiaced Aeptaaed Aspera ed Qepatwf Aspiaced Aspired Qephmd Qeptaced Replaced Aepleced Aepleced Qephoed Qep4aed Qep baaed Qe paired Qepleoed Rep~Rgdaced Aepteced ISOME'IRIC NO.FIG-1-9 SYSTEH REACTOR VESSEL CLASS 1 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEH COMPONENT NUHBER IDENTIFICATION COHPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI DATA SET.RI GEO OTHER NUMBER REMARKS LUG-01 LUG-02 LUG-03 LUG-04 LUG-05 LUG-06 LUG-07 LUG-08 LUG-09 CSB-L-1 CSB-L-2 CSB-L-3 CSB-L-4 CSB-L-5 CSB-L-6 CSB-L-7 CSB-L-8 CSB-L-9 CSB LUG 1 9 30 deg.CSB LUG 2 9 70 deg.CSB LUG 3 9 110 deg.CSB LUG 4 9 150 deg.CSB LUG 5 0 190 deg.CSB LUG 6 9 230 deg.CSB LUG 7 6 270 deg.CSB LUG 8 9 310 deg.CSB LUG 9 6 350 deg.B13.30 B13.30 B13.30 B13.30 B13.30 B13.30 B13.30 B13.30 B13.30 B-N-2 B-N-2 B-N-2 B-N-2 B-N-2 B-N-2 B-N-2 B-N-2 B-N-2 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 VT-3 IS I-072 X ISI-072 X ISI-072 X ISI-072 X ISI-072 X ISI-072 X ISI-072 X ISI-072 ISI-072 X 072-1 072-9 072-8 072-5 072-6 072-7 072-4 072-3,6 10 072-2 ACCEPTABLE ACCEPTABLE ACCEPTABLE ACCEPTABLE ACCEPTABLE ACCEPTABJ E ACCEPTABLE BURR 8 BOTTOM OF LUG ACCEPTABLE TEST PACKAGE NO.1-IPT-02 SYSTEM SIS IDENTIFICATION LOOP 1Al SIS ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1'Tue Aor INSTRUMENTED INSPECTION TECHNIQUE-IIT H A.F.A DESIGN 24b5 1985 PRESSURE TEST

SUMMARY

REPORT EXAMINATION TABLES TEST 1450 22 1986 PSIG 650 PSIG AMB.Beg e deg ITEM NO.ITT-7 ITT-8 ITT-9 ITT-10 ITT-11 ITT-13 ITT-14 ITT-15 ITT-16 ITT-18 ITT-19 ITT-20 ITT-21 ITT-22 ITT-24 ITT-25 ITT-27 ITT-28 ITT-30 ITT-31 ITT-32 ITT-33 ITT-34 ITT-36 ITT-37 ITT-38 ITT-39 ITT-40 ITT-41 LINE NUMBER 12-SI-102 12-SI-148 6-SI-112 6-SI-112 SEE DESC.2-SI-132 2-SI-272 N/A N/A 12-SI-101 12-SI-149 6-SI-113 6-SI-113 SEE DESC 2-SI-131 2-SI-271 N/A N/A 12-SI-103 12-SI-150 6-SI-111 6"SI-ill SEE DESC 2-SI-237 2-SI-133 N/A N/A N/A N/A TO V-3225 TO V-3227 TO PEN NO.37 , FROM P-37 TO V3124 3-SI-139&2-SI-132 TO HCV-3626 TO HCV-3627 LINES LESS THAN 2" OUTSIDE EXAM BONUND TO V-3215 TO V-3217 TO PEN NO 36 FROM P-36 TO V-3114 3-SI-140&2-SI"126 TO HCV-3616 TO HCV-3617.VENT, DRAIN, INST.OUTSIDE EXAM BOUND TO V-3235 TO V-3237 TO PEN NO.38 FROM P-38 TO V-3134 3-SI-138&2-SI-145 TO HCV-3637 TO HCV-3636 VENT, DRAIN, INST OUTSIDE EXAM BOUND VENT, DRAIN, INST.OUTSIDE EXAM BOUND B15.51 B15.51 B15.51 B15.51 B15.51 B15.51 B15.51 B15 51 C7.40 B15.51 B15.51 B15.51 B15.51 B15.51 B15.51 B15.51 B15.51 C7.40 B15.51 B15.51 B15.51 B15.51 B15.51 B15.51 B15.51 B15.51 C7.40 B15.51 C7.40 B-P B-P B-P B-P B-P B-P B-P B-P C-H B-P B-P B-P B-P B-P B-P B-P B-P C-H B-P B-P B-P B-P B-P B-P B-P B-P C-H B-P C-H DESCRIPTION CODE ITM CODE NUMBER CATEGORY EXAMINATION METHOD VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2'T-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT"02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 1-IPT-02 X X X X X X-X X , X X X X X X X X X X X X X X X X X TEST PROC NUMBER NRI.RI GEO OTHER DATA SHT'NUMBER 12.8-1 12.8-1 12.8-1 12.8.1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-1 12.8-2 12.8-2 12.8-2 12.8-2 12.8-2 12.8-2 12.8-2 12.8-2 12.8-2 12.8-2 12.8-2 CLASS HOLD TIME 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2s 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS TEST PACKAGE NO.1-IPT-04 SYSTEM.CVCS IDENTIPICATION LETDOWN IN.CTMT ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 INSTRUMENTED INSPECTION TECHNIQUE-IIT H.A.P-A 1985 PRESSURE TEST

SUMMARY

REPORT EXAMINATION TABLES Tue Apr 22 1986 DESIGN 2485 PSIG 650 deg.TEST 2235 PSIG AMB*deg ITEM NO.LINE NUMBER DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC.TEST PROC NUMBER NR I DATA SHT.CLASS HOLD RI GEO OTHER.NUMBER TIME ITT-1 ITT-2 ITT-3 ITT-4 ITT-5 ITT-6 2-CH-100 2-CH-103 2-CH-103 2-CH-128 2-CH-143 2-CH-142 RGX&V2516 TO P-26 RGX&V2516 TO P-26 P-26 TO V2342&2344 P-26 TO U2342&2344 P-26 TO V2342&2344 P-26 TO V2342&2344 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C-H C-H C-H C-H C-H C-H VT-2 VT-2.VT-2 UT-2 VT-2 VT-2 12.8 12.8 12.8 12.8 12.8 12.8 1-IPT"04 1-IPT-04 1-IPT-04 1-IPT-04 1-IPT-04 1-IPT-04 X X X X X X 12.8-3 12.8-3 12.8-3 12.8-3 12.8-3 12'-3 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS TEST PACKAGE NO.1-IPT-05 SYSTEM CH PUMP SUCTION IDENTIPICATION CHARGING PUMP ST.LUCIE NUCLEAR POWER Pf ANT, UNIT NO.1 Tue Apr INS'IRUMENTED INSPECTION TECHNIQUE-IIT H.A.P.A DESIGN 200 1985 PRESSURE TEST

SUMMARY

REPORT EXAMINATION TABf ES TEST 130 22 1986 PSIG 200 PSIG AMB deg o deg ITEM NO.LINE NUMBER DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC TEST PROC NUMBER NR I RI GEO OTHER DATA SHT NUMBER CLASS HOLD TIME ITT-42 ITT-43 ITT-44 ITT-45 ITT-47 ITT-48 ITT-49 ITT-50 ITT-51 ITT-52 ITT-53 ITT-54 ITT-55 ITT-56 ITT-57 ITT-58 ITT-59 ITT-60 ITT-61 ITT-62 ITT-63 ITT-64 ITT-65 ITT-66 ITT-67 ITT-68 ITT-69 ITT-70 ITT-71 ITT-72 ITT-73 ITT-74 3-CH-937 3/4-CH-962 3-CH-939 SEE DESC 4-CH-368 3-CH-801 1.5-CH-558 1/2-CH-957 1-CH-A15 3/4-CH-A41 1/2-CH-966 1/2"CH-194 3-CH-593 1-CH-193 4-CH-967 2-CH-532 1/2-CH-534 1/2"CH-381 1/2-CH-536 1/2-CH-535 4-CH-947 2-CH-538 1/2-CH-948 1/2-CH-382 1/2-CH-541 1/2"CH"540 4-CH-368 2-CH-543 1/2-CH-542 1/2-CH-382 1/2-CH-545 1/2"CH-546 PROM V2509 TO V2508 TO V-2877 TO V-2190 3-CH-944 6 4-CH-544 TO V-2118 TO V-2514 TO V-2180 TO V-2311 TO V-2174 TO V-2845 TO V-2308, TO V-2838 TO V-2191 TO V-2837 TO V-2316 TO V-2326 TO V-2315 TO V-255Q TO V-2437 TO V-2317 TO CHG.PUMP 1B TO V-2325 TO V-231&TO V-2551 TO V-2438 TO V-2320 TO V-2322 TO V-2324 TO V-2321 TO V-2552 TO V-2323 TO V-2439 Cj.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C"H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT"2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-Q5 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 1-IPT-05 X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X X 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12~8" 4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 12.8-4 2 2 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS+S 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS 2 HRS-2 HRS TEST PACKAGE NO.1-IPT-06 ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 SYSTEM CH PUMP DISCHARGE INSTRUMENTED INSPECTION TECHNIQUE-IIT H.A.P.A IDENTIFICATION CHARGING PUMP 1985 PRESSURE TEST

SUMMARY

REPORT EXAMINATION TABLES Tue Apr 22 1986 DESIGN 2735 PSIG 250 deg.TEST 2335 PSIG AMB deg ITEM NO.LINE NUMBER DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC.TEST PROC NUMBER NRI RI GEO OTHER DATA SHT CLASS HOLD NUMBER TIME ITT-75 ITT-76 ITT-77 ITT-78 ITT-79~ITT-80 ITT-81 ITT-82 ITT-83 ITT-84 ITT-85 ITT-86 ITT-87 ITT-88 ITT-89 ITT-90 ITT-91 ITT-92 ITT-93 ITT-95 ITT-96 ITT-97 ITT-98 ITT-99 ITT100 2.5-CH-111 2-CH-112 2-CH-125 2-CH-346 2-CH-126 2-CH-127 2.5-CH-110 2-CH-109 2-CH-BOO 2.5-CH-107 2.5-CH-106 2-CH-.104 2-CH-135 2-CH-136 2-CH-137 N/A N/A N/A I-V02304/2305 V-2818 V-2427 V-2428 V-2425 SEAL TANK V-2803 N/A TO I-SE-02-02 TO I-SE-02-03 TO I-SE-02-04 TO I-SE-02-01 TO V>>2435&V-2434 TO I-MV-02-2 THROUGH PEN.NO.27 TO I-MV-02-1 N/A N/A TO VO-2134 TO I-V02132&V-2338 TO V-02133 TO V-2340&2-CH-135 VENTtDRAINt INST VENT, DRAIN&INST.VENT, DRAIN, INST VENT, DRAIN, INST.VENT~DRAIN,INST.

VENT,DRAINtINST.

VENTtDRAINtINST VENT,DRAINgINST.

OUTSIDE EXAM BOUND OUTSIDE EXAM BOUND C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C7.40 C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H C-H VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 12.8 12'12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 12.8 1-IP T-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 1-IPT-06 X X X X X X X X X X X X X X X X X X X X X X X 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 12.8"5 12.8-5 12.8-5 12.8-5 12.8-5 12.8-5 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2~2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS 2 2 HRS TEST PACKAGE NO.1-IPT-01 SYSTEM RCS IDENTIFICATION PRI.HYDRO TEST ST.LUCIE NUCLEAR POWER Pf ANT, UNIT NO.'1 1985 PRESSURE TEST

SUMMARY

REPORT EXAMINATION TABf ES Tue Apr 22 1986 DESIGN 2485 PSIG 650 deg.TEST 2295 PSIG 500 deg ITEM NO.LINE NUMBER DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGOR Y METHOD PROC.TEST PROC NUMBER NR I DATA SHT.CLASS HOLD RI GEO OTHER NUMBER.TIME HYD-01 HYD-02 HYD-03 HYD-04 HYD-05 HYD-06 HYD-07 HYD-08 HYD-09 HYD-10 HYD-11 HYD-12 HYD-13 HYD-14 HYD-15 HYD-16 HYD-17 30-RC-112 42-RC-114 30"RC-115 30"RC-121 42-RC-123 30-RC-124 4-RC-101 4-RC-103 12"RC-108 12-RC-147 12"RC-151 PRZ~RELIEF SEE DESC 3-RC-109,&141 N/A lA&1B lAl,lA2,181,1B2 30 RCS PIPING HOT LEG 30" PIPING 30" PIPING HOT LEG PIPING 30" PIPING PRESSURIZER RELIEF PRESSURIZER SPRAY PRESSURIZER SURGE SHUTDOWN COOLING 12-RC-152,152,154 2.5-RC-156,157 VENT, DRAIN, INST PRZ~SPRAY IINE PRESSURIZER STEAM GENERATOR A&B RCP PUMPS B15~51 B15.51 B15.51 815.51 B15.51 B15.51 B15.51 B15.51 815.51 B15.51 B15.51 B15.51 B15.51 815.51 B15.21 B15.31 B15.61 8-P B-P B-P B"P B-P B-P B-P B-P B"P B-P B-P B-P B-P B-P B-P B-P B-P VT-2 VT-2 VT-2 VT-2 VT"2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 VT-2 9.9-2.1 9.9"2.1 9.9-2.1 9.9-2.1 9.9-2.1 9.9-2.1 9.9-2.1 9.9-2'9.9-2.1 9.9-2.1 9'-2.1 9.9-2.1 9.9",2.1 9.9-2.1 9.9-2.1 9.9-2.1 9.9"2.1 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01.1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 1-IPT-01 X X X X X X X X X X X X X X X X X M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-'?486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 M-85-7486 1 4 HRS 1 4 HRS 1 4 lfRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS 1 4 HRS ISOMETRIC NO.A-09 SYSTEM PRESSURIZER CLASS 1 1985 INSERUICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COHPON ENT NUMBER IDENTIPICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM DATA SHT.NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 000090 PRZ HANWAY BOLT 20 STUDS 6 20 NUTS B2.11 B-G-2 VT-1 9.9-1.1 X M-85-6893 ISOMETRIC NO.A-12 SYSTEM STEAM GENERATOR A CLASS 1 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUMBER IDENTIPICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT.GEO OTHER NUMBER REMARKS 4 000121 SG-lA BOLTING MANWAY NO.1 0 deg B3.10 B-G"2 VT-1 9.9-1.1 X M-85-7405 ISOME'IR IC NO.A-25 SYSTEM REACTOR COOLANT CLASS 1 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue APr 22 1986 ITEM COMPONENT HUMBER IDEHTIRICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT.GEO OTHER NUMBER REMARKS 001288 VALVE CV-3217 16 STUDS 6 16 HUTS B6.9 B-G-2 VT-1 9.9-1.1 001296 MV-3614 12" GATE VALVE BOLT.B6.9 B-G-2 VT-1 9.9-1~1 X M-85-6965 FLANGE LEAKING X M-85-6964 M-85-7023i7026 ISOMETRIC NO.A-26 SYSTEM RC CLASS 1 1985 INSERV'ICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUMBER IDENTIFICATION COMPONENT DESCRIPTION CODE ITH CODE EXAMINATION NUMBER CATEGORY METHOD EXAM PROC NRI RI DATA SHT-GEO OTHER NUMBER REMARKS 001304 VALVE MV-3480 16 STUDS&16 NUTS 001342 VALVE V-1215 4 STUDS 6 4 NUTS B6~9 B6.9 B-G-2 B-G-2 VT-1 VT-1 9.9-1.1 X 9.9-1.1 H-85-6875 X H-85 6966 EVIDENCE OP LEAKING>

ISOMETRIC NO.A-28 SYSTEM REACTOR COOLANT CLASS 1 1985 IHSERVICE INSPECTION

SUMMARY

REPORT, EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUMBER IDEHTIPICATIOH COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI B-G-2 VT-1 9.9-1.1 001347 VALVE V-2431 4 STUDS 6 4 NUTS B6.9 DATA SHT GEO OTHER NUMBER~REMARKS X M-85-7325 BORIC ACID ISOMEIRIC NO.A-31a SYSTEM CVCS CLASS 1 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEN COMPONENT NUMBER IDENTIFICATION COMPONENT DESCRIPTION 000635 2-CH-145-9PR PIPE RESTRAINT B4.10 B-K-2 VT-3 9.9-3.1 X CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD , PROC NRI RI DATA SHT.GEO OTHER NUMBER H-85-7145 REMARKS ISOHE'IR IC NO.A-34 SYSTEM CVCS CLASS 1 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEH COMPONENT'NUHBER IDENTIPICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT.GEO OTHER NUHBER REMARKS 001348 VALVE CV-2432 4 STUDS Ec 4 NUTS 000770 2-CH-148-9PR PIPE RESTRAINT B6.9 B4.10 B-G-2 B-K-2 VT-1 VT-3 9.9-1.1 X 9.9-3.1 X H-85-7338 M-85-7160 I~~P ISOMETRIC NO.A-37a SYSTEM SIS CLASS 1 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PI,ANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUMBER IDENTIPICATION COHPONENT DESCRIPTION 001085 6-SI-112-46PR PIPE RESTRAINT B4.10 B-K-2 VT-3 9'-3.1 X CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT.GEO OTHER NUMBER'-85-6796.REMARKS

~.g ISOMFIRIC NO.A-38 SYSTEM SIS CLASS 1 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PI ANTi UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT COMPONENT NUMBER IDENTIPICATION DESCRIPTION 001312 VALVE CV-3114 VALVE BOLTING 12 001101 6-SI-113-llPR PIPE RESTRAINT N/B B6.9 B4.5 B"G-2 B-K-2 VT-1 VT-3 9.9-1.1 9.9-3.1 CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT.GEO OTHER NUMBER REMARKS X M-85-6729 HEAVY BORON BUILDUP X M-85-7020 LOOSE BOLTS ISOMETRIC NO.A-39/40 SYSTEM RCP CLASS 1 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABL ES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUMBER IDENTIFICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT.GEO OTHER NUMBER REMARKS 001285 RCP-1B2 1ST.SEAL BOLTING B5.9 B-G-2 VT-1 9.9-1.1 X H-85-6890 ISOMFIRIC NO.B-4 SYSTEM SHE CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986'TEH COMPONENT NUMBER IDENTIFICATION COMPONENT DESCRIPTION CODE ITH CODE EXAMINATION EXAM DATA SHT.NUHBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001453 SHE-lA OUTSIDE FLANGE BOLTS C1.4 C-D VT-1 9.9-1.1 X M-85-6731 48 STUDS,96 NUTS ISOMETRIC NO.B-06 SYSTEM MS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 L Tue Apr 22 1986 ITEH COMPONENT NUMBER IDENTIPICATION COMPONENT DESCRIPTION CODE ITM CODE EXAHINATION EXAM DATA SHT.NUMBER CATEGORY=-METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001514 34-MS-28-5PR 001507 34-HS-28-1PR 001525 34-HS-28-10PSS PIPE RESTRAINT PIPE RESTRAINT PIPE SUPPORT C2.6 C2.6 C2.6 C" E-2 C-E-2 C-E-2 VT-3 9.9.-3.1 X VT-3 9.9-3.1 X VT-3 9.9.-3.1 X M-85-6868 H-85"6867 M-85-6866 1 a~

ISOMETRIC NO.B-Q7 SYSTEM MS CLASS 2 1985 INSERVICE INSPECTION SUHHARY REPORT EXAMINATION TABLES ST.LUCIS NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUMBER IDENTIPICATION COMPONENT DESCRIPTION 001541 34-MS-29-5PR PIPE RESTRAINT CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI C2.6 C-E-2 VT-3 9.9-3.1 X DATA SHT.GEO OTHER NUMBER , REMARKS M-85-6858 ISOHBIRIC NO.B-08 SYSTEM HFW CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUMBER IDENTIFICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI DATA SHT.RI GEO OTHER NUMBER , REMARKS AUG-Ol 18-BF-51-2A NOZZLE TO SAFE END C5.21 AUG-2 18-BF-51-2B SAFE END TO ELBOW C5.21 AUG-3 18-BF-51-3A ELBOW TO PIPE C5~21 C-F C-F C-F UT UT UT 5.16 5.16 X 5.16 5.16-1 5.16-1 5.16-1 AUGMENTED EXAM AUGMENTED EXAM AUGMENTED EXAM ISOMETRIC NO.B-09 SYSTEM HFW-CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANTi UNIT,NO.1 Tue Apr 22 1986 ITEM NUMBER COMPONENT'DENTIFICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI DATA SHT RI GEO OTHER NUMBER~REMARKS AUG-5 001611 AUG-3 AUG" 6 001621 18-BF-52-2B 20-BF-19-6PR 18-BF-52-2A 18-BF-52-3A BFH-76A SAFE END TO ELBOW PIPE RESTRAINT NOZZLE TO SAFE END ELBOW TO PIPE PIPE RESTRAINT BF-M6 C5.21 C2.6 C5.21 C5.21 C2.6 C-F C-E-2 C-F'-F C-E-2 UT VT-3 UT UT VT-3 5.16 X 9.9-3.1 X 5.16 5.16 9.9-3.1 X X X 5.16-1 AUGMENTED EXAM M-85-6859 5.16-1 AUGMENTED EXAM 5.16-1 AUGMENTED EXAM M"85-6857 ISOMETRIC NO.B-10 SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT COMPONENT, CODE ITM CODE" EXAMINATION EXAM NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD.PROC NRI RI 002175 VALVE V-07-1555 BOLTING 20 STUD,40 N C4.2 C-D VT-1 9.9-1.1'-DATA SHT.GEO OTHER NUMBER~REMARKS X H-85-6727 BORON ACCUMULATION ISOMETRIC NO.B-11 SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION SUMHARY REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI 002174 VALUE 07-1555 BOLTING 20 STUD,40 N C4.2 C-D VT-1 9.9-1.1 DATA SHT.GEO OTHER NUMBER REMARKS X M-85-6724 EVIDENCE OF LEAKAGE ISOMERIC NO.B-12 SYSTEM SIS CLASS 2'985 INSERVICE INSPECTION SUHHARY REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT COMPONENT NUMBER IDENTIFICATION DESCRIPTION 002178 VALVE FCV-3306 VALVE BOLTING CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI C4~2 C-D VT-1 9.9-1.1 X DATA SHT-GEO OTHER NUMBER.REMARKS H"85-6723 40 STUDS, 40 NUTS ISOMETRIC NO.B-13 SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986" ITEM COHPONENT NUMBER.IDENTIFICATION COMPONENT DESCRIPTION CODE ITH CODE EXAHINATION EXAM NUMBER CATEGORY-METHOD PROC NRI RI DATA SET.GEO OTHER NUHBER 002185 VALVE V-3456 VALVE BOLTING C4.2 C-D VT-1 9.9-1.1 X M-85-6725 8 STUDSi 8 NUTS ISOMETRIC NO.B-17 SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT'XAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUMBER IDENTIPICATION COHPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT.GEO OTHER NUMBER REMARKS 002183 VALVE 3452 VALVE BOLTING C4.2 C-D VT-1 9.9-1.1 X M-85-6726 8 STUDS, 8 NUTS ISOMETRIC NO.B-19 SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apz 22 1986 ITEM COMPONENT NUMBER IDENTIPICATION COMPONENT DESCRIPTION 001844 12-SI-477-5PR PIPE RESTRAINT CODE ITM CODE EXAMINATION EXAM NUHBER CATEGORY METHOD PROC NRI RI C2.6 C-E-2 VT-3 9.9-3.1 DATA SHT.GEO OTHER NUMBER REMARKS X M-85-6736 REPAIREDN REALIGNED ISOME'IRIC NO.B-20 SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI QQ2181 VALVE V-3206 BOLTING 8 STUDS/NUTS C4.2 C-D" VT-1 9.9-1.1 DATA SHT.GEO OTHER NUMBER REMARKS X M-85-6728 EVIDENCE OP LEAKAGE ISOMETRIC NO.B-21 SYSTEM SIS CLASS 2'985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEN COMPONENT NUHBER IDENTIFICATION COMPONENT-DESCRIPTION CODE ITH CODE EXAMINATION EXAM DATA SET.NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001949 10-SI-420-16PR1 001941 10-SI-420-11PR1 001926 10-SI-420-11PR1 001958 10-SI-420-22PR PIPE RESTRAINT PIPE REST.SIH-223 PIPE RESTRAINT PIPE RES'IRAINT C2.6 C2.6 C2.6 C2.6 C-E-2 C-E-2 C-E-2 C-E-2 VT-3 VT-3.VT-3 VT-3.9.9-3.1 9.9-3.1 9.9-3.1 9.9-3.1 X X M-85-6891 X M-85-6963 REALIGNED H-85-7265'M-85-6892 ISOMETRIC NO.B-2la SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEH COMPONENT NUMBER IDENTIPICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT GEO OTHER NUMBER REMARKS 001990 10-SI-420-48PR PIPE RESTRAINT 001997 10-SI-420-52PR PIPE RESTRAINT C2.6.C2~6 C-E"2 C-E-2 VT-3 VT-3 9.9-3.1 9.9-3.1 X H-85-6732 LOOSE WASHERS X H-85-6734 HISSING NUTS ISOMETRIC NO.B-22 SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986'TEM COMPONENT NUMBER IDENTIFICATION COMPONENT DESCRIPTION CODE ITM CODE EXAMINATION EXAM~DATA SHT.NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 002025 10-SI-422-15PR PIPE RESTRAINT 002013 10-SI-422-6PR PIPE RESIRAINT C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6795 ACCEPT AS-IS C2.6 C-E-2'T-3 9.9-3.1 X M-85-6876 ISOME'IRIC NO'.B-22a SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22 1986 ITEM COMPONENT NUHBER IDENTIFICATION COMPONENT DESCRIPTION CODE ITH CODE EXAMINATION EXAM NUHBER CATEGORY METHOD PROC NRI RI DATA SHT.GEO OTHER NUHBER REMARKS 002056 10'-SI-422-39PR1 PIPE RESTRAINT 002057 10-SI-422-39PR2 PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6767 C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6769 ISOMETRIC NO.B-23 SYSTEM SIS CLASS 2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST-LUCIE NUCLEAR POWER PLANT, UNIT NO~1 Tue Apr 22 1986 ITEM COMPONENT COMPONENT NUMBER IDENTIFICATION DESCRIPTION 001320 HCV-3615 6 GLOBE VALVE BOLT 002108 6-SI-409-2PLS (2)SUPPORTS 1 6 2 C4.2 C2.6 C-D C-E-2 VT-1 VT-3 9.9-1.1 X 9.9-3.1 CODE ITM CODE EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NR I R I DATA SHT.GEO OTHER NUMBER REMARKS't M-85-6730 X'-85-6735 ACCEPT USE AS-IS ISOMERIC NO.B-24 SYSTEM SIS CLASS.2 1985 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION TABLES ST.LUCIE NUCLEAR POWER PLANT, UNIT NO.1 Tue Apr 22*1986 ITEM COMPONENT NUMBER IDENTIFICATION COMPONENT DESCRIPTION CODE ITM CODE ,.EXAMINATION EXAM NUMBER CATEGORY METHOD PROC NRI RI DATA SHT, GEO OTHER NUMBER REMARKS 002138 6-SI-462-9PR PIPE RESTRAINT C2.6 C-E-2 VT-3 9-9-3.1 X 002131 6-SI-462-2PR PIPE RESTRAINT SIH96 C2.1 C-E-2 VT-3 9.9-3.1 M-85-6733 X M-85-7468 DOES NOT EXIST