ML17216A510
| ML17216A510 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/25/1986 |
| From: | Liallo C, Uvaba J ARKWRIGHT BOSTON MANUFACTURER'S MUTUAL INSURANCE, FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17216A509 | List: |
| 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 Manufacturer Manufacturer State or National Appurtenance or Installer or Installer Province Board Serial No. Number Number RPV VESSEL Combustion Eng. N A N/A N/A PRESSURIZER Combustion Eng. N/A N/A N/A STM. GEN. A & B Combustion Eng. N/A N/A N/A REACTOR COOLANT Ebasco 2"-RC-142 N A N A SAFETY INJECTION Ebasco 6"-SI-112 N A N A 6"-SI-113 12"-SI-477 10"-SI-420 10"-SI-422 6"-SI-409 6"-SI-462 CVCS Ebasco 2"-CH-148 N/A N/A.
MAIN STEAM Ebasco 34"-MS-28 N A N A 34"-MS-29 FEEDWATER Ebasco 20"-BF-19 N/A N A 18"-BF-51 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 8s04~0 05000gS PDR ADO'~ PDR 6
'7 1
page 2 of 14 NIS-1 REPORT CONTINUED 8.Examination Dates I 10-20-85 to 12-24-85
- 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.
leakage 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
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 their control valves. Two (2) needed slight adjustment and two (2) orifice'n 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 INJECTION LOOP 1Al lA2 g g lBli 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 Report during the period 20 Oct 1985 to 24 Dec 1985 Owners'ata
, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Report in accordance with the requirements of the ASME Code, Owners'ata 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 FACTORY MUTUAL SYSTEM Commissions NB-7719 Inspector's Signature National Board, state, Province and No.
- ARKWRIGHT BOSTON MFG'S MUTUAL INSURANCE COMPANY
I 1 r 0
NIS-1 REPORT CONTINUED page 8 of 14 SUPPLEMENTAL SHEET NIS-1
- 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 FPL INSERVICE INSPECTION FINAL REPORT OF AUGMENTED, ISI ON FEEDWATER PIPING NO NUMBER ASSIGNED FPL EDDY CURRENT EXAMINATION OF STEAM GENERATORS CEN-326 (F) CE FINAL CORE SUPPORT BARREL INSPECTION REPORT POST CYCLE SIX 1-IPT-02 FPL TEST DOCUMENTATION ON (IIT) 1-IPT-04 INSTRUMENTED INSPECTION 1-IPT-05 TECHNIQUE 1-IPT-06
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 TOTAL TOTAL TOTAL TOTAL TOTAL GENERATOR TUBES INDICATIONS INDICATION INDICATION TUBES NUMBER INSPECTED 20% OR = TO OR = TO PLUGGED 20% TO 39% 40% 100%
II S/G A 8166 N/A 263- 48 46 II S/G B II 8214 N/A 109 20 19 LOCATION OF INDICATIONS STEAM FULL PARTIAL TOP OF TUBE SHEET GENERATOR BATWINGS EGGCRATES EGGCRATES TO 1 DRILLED SUPPORT 1 THRU 8 9 AND 10 II G All NONE 54 47 211 S/G IIBII 22 14 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: Date 4-25-86 name FLORIDA POWER & LIGHT CO.
address P.O. BOX 529100 MIAMI'LORIDA33152 sheet 10 of 14
- 2. Plant: Unit 1 name ST. LUCIE NUCLEAR PLANT address P.O. BOX 128 PC/M NO. 180-185 FT. PIERCE, FL 33454 repair organization P.O. No.
job No., etc.
- 3. Work Performed by: Type Code Symbol Stamp N/A name PAUL MUNROE address 1701 W. SEQUOIA AVE Authorization no. N/A P.O. BOX 5900 ORANGE, CALIFORNIA 92668 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 Name of Mfrs. Ser. Nat'1 Crn Other Year Repaired ASME Code Component Mfr. No. Bd. No. Ident- Built Replaced stamped No. ifica- or repl- (yes,no) tion acement STM. GEN ITT MODEL NO. MODIF-SNUBBER GR INNEL BH-1224 N/A N/A 1-001 N/A IED YES MODIF-N/A N/A 1=002 N/A IED YES REACTOR 1-017 MODIF-COOLANT N/A N/A 1-018 N/A IED YES PUMP 1-019 REPLA-N/A N/A 1-.020 N/A CED 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 4-2 '-8 FLORIDA POWER & LIGHT CO. BY (- a-C(
(Owner or Owner's Designee) (Title) (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 Commissions FACTORY MUTUAL SYSTEM (Inspector) COMM. NO NB- 7719 (State or Province, National Board)
- ARKWRIGHT BOSTON MFG'S MUTUAL INSURANCE COMPANY
NIS-2 SUPPLEMENTAL SHEET PAGE 12 OF 14
- 4. IDENTIFICATION STEAM GENERATOR 6 REACTOR COOLANT PUMP ITT GRINNELL OF SYSTEM: FIGURE 20 0 g 5 STROKE HYDRAULXC PXSTON CYUNERS WITH MODEL BH-1224 DUAL ORIFICE TYPE LOCK UP VALVES
- 7. DESCRIPTION OF WORK: 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 1-001 SS-1 1A MODIFIED 1-002 SS-2 1A MODIFIED REACTOR COOLANT 1-017 lAl MODIFIED PUMP 1-018 1A2 MODIFXED 1-019 1Bl REPLACED 1-020 1B2 REPLACED 12
NIS-2 SUPPLEMENTAL SHEET PAGE 13 OF 14 1.OWNER: FLORIDA POWER & LIGHT COMPANY DATE: 4-25-86 P.O. BOX 529100 MIAMI, FLORIDA 33152 2.PLANT: ST. LUCIE NUCLEAR PLANT UNIT: 1 P.O. BOX 128 FT. PIERCE, FLORIDA, 33454
- 3. WORK PAUL MUNROE JOB NO. 172-185 PER FORMED BY:
4.IDENTIFICATION MECHANICAL SNUBBER END ATTACHMENT WITH OF SYSTEM: SPACER AND BUSHING PROBLEMS 7.DESCRIPTION PROVIDE MECHANISM TO ELIMINATE THE EXCESSIVE OF WORK: CLEARENCE BETWEEN THE PINHOLE OF PIPE CLAMPS BRACKETS AND THE SNUBBER PINS. THIS MECHANISM WILL
/ END ALSO ELIMINATE THE EXCESSIVE GAPS BETWEEN THE PIPE CLAMP HALVES AND THE ROD END BUSHINGS.
SNUBBERS AFFECTED BY THIS MODIFICATION:
MANUFACTURER TYPE LINE NO. FPL TAG PACIFIC PSA-3 RC-005-34A 1-021 SCIENTIFIC PSA-3 RC-005-34B 1-022 PSA-10 RC-005-12A 1-024 PSA-10 RC-005-55C 1-028 PSA-3 "RC-005-62A 1-029 PSA-3 RC-005-90 1-031 PSA-10 BF-661-407 1-048 PSA-10 BF-661-407 1-049 PSA-3 SI-968-1205 1-055 PSA-3 SI-969-6193 1-059 PSA-3 SI-969-6195 1-060 PSA-3 SI-973-, 240 1-074 PSA-3 CC-1899-48 1-097 PSA-3 CH-64-40 1-106 PSA-0.25 RC-5-475 1-121 PSA-0.25 CH-129-99 ,
1-122 PSA-1 RC-1-124A 1-148 PSA-0.25 CH-142-18 1-160 PSA-0.25 CH-141-44A 1-191 PSA-3 CC-1899-2200 1-202 13
St. Lode Unit ~$
hssrvtce Irxeecttm-Oct - Dec)965 Seemly of Sca4ber Anoeaoltss Requtrlng Corrects AcQae Toy trek Fwctionel Test Nurnhcr the)hr Aeeeltes lml ~SS-1 IA H/A Control Valve Rsyatrad
~
m-200'TT-200.00 SS-2 IA SL N/A Control Vahe Qspatred HC5 l~
l~ S&4 IA S&4 )A 1A ITT-20030 AT-20080 NA H/A H/A N/A-Control Vahe Control Vahe Gets Valve Qopatrad Aspsrfred Act&red I~
1~
S&4 IA SS-7 IA Ili-200'T-200'TI-200AXI Nk Nk HtA N/A Control Valve trolVahe Qeyafred Rope)red
-I~ ~IA ITT-200AN NA N/A C
Control Vahe Repsdred HXS SS"I I8 iiT-200AM NA N/A Control'Valve Qepatrad 1&11 mQ
~
1&10 SS 2 IB
~IB IB AT-200 IlT-20040 NA NA NA, N/A N/A N/A Control Vahe Controt Valve Cm~l V~
ihydred Royal')
Repaired Ma ~IB
~
ITT-200'ii-200AM HA N/A Contr>A Valve QeyaIra0 1%14 IB NA, N/h Controi VAe Repaired N-200'TT-200AM I<% SS-7 IB NA N/A Control Vatve Aepatrad M16 ~IB AT-200'Tf~.00 NA N/A Consol Valve QeyaW4 1&17 ~ )A'I NA N/A (>gay 5 Aalease h+eted Hl" IA2 AT~.OO Nk N/A Aeteese rate fustad 148 < t51 ITT~.OO IIA N/A Ngh 4rag faQure AepIaced
'OO ~'182 HQI 'C~54L m'~.00 PSArB.OO NA, Qkerlcslbe~gdtslodped-8/A N/A
~
N/A dra9 fatIMre Qeytacad Aspatrod
~
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~RC~I2A 1~ ~jC~~
PSA-3'A PSALM AO PSA-10.00 PSA-IOAO
~ericelbsa Ing <%smudged.
QQrhtlbarhg 4sio49ed.
Syae Iceitea hgs~dtsytac d.
N/A N/h N/A H/h I/A N/A Aeyatrad Aepatrad Ibpeirad
~'RC~mea PSA-MN Qkaricelbearh94siodyed- N/h Hlh Aeyetrad S-ml JaCW~O Shrlcelbeehe dtslodged. N/A &eeeaat AQg Rsplacad
R.Lode Unit~i kesrvk>> lnspecUm-Oet. -Dac.. 1985 SLarxnary of Sekbsr Anosnslkes AequHng Ox receive Ac%as t&44Hi P Jfri55AO Qanp~hg. N/A H/A hddad spaoes.
l~
$ ~
M34
~$
ff&64M14 07&5164 PSA-35'SA&.00 PJJ!@%ATE Chep sgechg.
Sphsrlcalbearhg crade0 Pip>> dssnp bonny hase.-
H/h l4/h Nfh
%'h N/h N/A Added W~es.
Asp air>>d f4gekad 1~ ~%~1~? PSA-10.00 '~icNbearh94sWgad Nfh Aepalrad 1~ 8&461~
l~
't~ Sl~8"1205 SMQM195 PSA-10.00 PSA-3.00
~AS S14erkal bearhg dislodged Spterlcalb>>arlog 4sihxlg>>4 Sgarlcal boa4g 4smodged N/h tl/A 8/A N/A H/A H/A Repaired A>pair>>d Aep>>Wd SMRH5$ 95 PSA&.00 Sgbsrkal 0>>arhydhlodgad. l4/h H/h RgeW4 1~ S1~
SWATS-)27 PSA-10.00 Oat on eAbsr body Il/A Lin@e4sh4e 'fbylacad 8&971~ 12'70 PSAri5AO NA Ssvbbar 14/A Aplacwl M?4'l~240 l~
l~?. CC-1%&4)
PSALM PSA-10.00 PSALM Qjbarkalbaarhg d}slodgsd.
PaNe hhd: T ahelW~C.
Spb>>rlcalberhg east&ed.
N/A NIA N/A Beetled AQg H/h
&ceeded .02g lbgHacad Asp aired Asplaced HO'1 0C-l?-l PSA-T0.00 NA N/A FaQ>>d to odheta Qepla cad 1-106 CH~O Sph<<kal herby Os)+led. 8/A N/h Qgehwl 1-11? AC-1 221 A 1-1 18 RC-1-1M'-120 PSALM AO PSH)28
~2S HA NA NIA Nfh
~ drag fallow Ngh drag falter>>
Qeplacad Qeplac>>d RC-1-192A PSA2S NA N/A Ngh drag Mare Replaced 1-121- Sr&4?S ~25 Over,shed hob 1n damp. N/A 8/h hddedbu&lng 1-122 CH-l~ ~25 Overahsd bola hc}cap. N/A N/h AddedhusNg Ngh 4 ag Mora 1-123 RC-21?%
1-'l24 - OHiSfi4C 1-DS CH-M&9 PSA2S
~25 PSA&2S NA NA Nh N/A N/A Ngb ~
H drag false ftQura Qeplaced A<placed Replaced 1-126 CH-14bRC N/h lo test Rsgaced 1-12? AC<'l&9A PSAr02S PSA&25 Nh HA N/h Ngh ~
Lockedrag>
faSF>> Replaael
~
~
St. Ludo Unit +1 b3sendce IeeeNon-Od. -Doe HBS Surgery of Qxkber AnamaNes Qequlrbg CetneUve Actus Opeak@ity Test fuoctio&Test Axealles hnwno5es 1-QS ~
I-'l20 ttQ-~
2&3A PSAr025 PSA26 Nh NA NIA N/A
~ dray fa9ure Ngh dray faQre 1-129 'L-1-$24: PSH725 NA Snab fheea High dray faire l-)30 ttQ-~ PSAO25 Nh NfA High 4ray fabbro 1-131. tSI-15-3A ~25 Nh NIA drag failure 1-U2 CH-1ÃrXi6 PSA&28 NA f Sabtwr ceca. Ngh drag faire 1-7Xf tSf-14-3A 7-134 CH-1~9 PSA&25
~2S NA Hk H/A N/A
~
~ dray faire 4ray faNre 1-137. CH-)2%459 RA<)2S NA S04bN'l'own.
1-Q8 AC-114-129 PSA25 NA N/A Ngh drag Mhre 1-139 AC-221-i62 1-140 CH-lN~
PSH)25 PS'$
Nh HA NIA N/A
~ dray fable f
High dray thre 1-141 - CH-145-26C l-l4
~25 -Q NIA High 4ray falkre CS-141-74 P8k025 -Nh N/A Ngh drag ASKS 1-14l P'M1 PSk425 Nh Qekbe thesn. Nfh 1-14' RC-18&8 PSA25 NA NIA locke}~ ln test 1-'l4$ .
CH-14'-145 AC-1-25C 1-MIRAC-1-%@A, PSA2S PSA25 PSA-lAN HA NA Sbberkalbeahg dIQodyed.
NIA Umnlted NfA
~ ~drayf ere NA'/A 1-149 1-150 l%H34A PSA-1AO PSA25 Nh NA r NfA NIA
~
~ dray faSre 4ray faH~
1-151. CH-142-17 PS~BS NA NIA Ngh 4ray false 1-)S4 ~fSl-l~ PSM)25 NA H/A ggh dray fafkre l-1SS 'C-1~9 PSA2S NA NfA , ~drayfahre 1-155 XQ-1244 PSA-02S NA N/A ~dray ANure 1-157 QC-21+45 PS&425 NA UmttN strobe 8/A
emtua 1 hsorvlce tnsyectlon -Oct. -Dec 198S Selaery oS Sefhar hnomo5sa Raquirloy Corrective Actus OpanhQfty Test hnctiael Test Anoae@os Aaomo?bs 1-158 CH-1~'l6 P8k425 NA Nfh Ngh drag f8~ Replaced 1-160 '>F18 PSH?2S erskned Me 4c~. -- N/A H/A Repleced l-l61'C-165-11 P8lr025 NA Stabber theat KIA Qpgrahs PSA-1 1-162 AG-217% PSA25 NA Unde stroke Ngh dray Cdlee Asplaaed 1-163 SM~) ~25 NA Nfh Ngb drag Whee Qsp1aced 1-164 Sl~ PS%425 NA N/h Ngh dray faStre Asg Baaed 1-16? Of67&1 PSA&2S NA N/A Ngh dray Mure Replaced AC-1 14-)2$ PSAO2$ Nh Nfh Ngh drag failure A~laced 1-169. $ C~26 PSH325 Nh N/A Ngb drag faSre Itiplaced 1-17 l AC-218-26 PSA&25 NA N/A f Ngh dray Huee ihg&cod 1-G2 AC~11 PSA&25 NA N/h Ngh dray faire Replace 1-1TS" OH%41 PS&)25 HA Nfh ~drag f Ore QIptaced 1-176 N-F41 PSA&2S HA, N/A Igh drag 5d~ Aephced l-)77 QC-22~ PSA2S NA N/A Sgh drag f4~ Aephced 1-176 ttS&H41 PSAr025 NA 8/A Sgh drag fibre Qsptaced 1-)60- AC-220-114 PSA&2S PadClesNiAy. N/A N/A @gested M82 AC-219%A
)-105" OSSA 1-186- 8-l~
PSA-1 AN PSA25 PSA-025 NA NA NA 8/A tlmttei ~
Sekha sheen.
Syhdray Qthre Ngh drag NIA M~
Aaplaaed Replaced 1-167 %94) ~2S NA Nfh egh dray retire 1-1$ 8" AC-1QHP PSA&2$ NA NIA Sgb drag feQre l-189 Q~iO Heeiy coreoelonmheelny. '/A ~drayr~
1-190, CH-Nl~ PSA2S NA NIA Ngh Oreg false 1-191~ CH 111~ ~25 Ieerlng4shdgad; muke5 hrekei. N/A N/A 1-194- fly-75 PSA25 NA Snye'aten.
1-195 ~ N%-200-250
~ e, (
~2$ NA 8/A Ngh drag falhre Pagel
St. Lode Unit J heorvlce iaseec5on -CcL, -Qec)985 Scenery of Satb+'AgaN5e Qequfrhg Cartvct4e A@Dam Tag Nark OpsrehBRy Test NNnba Neer Aamo5es
~25
~~
1-196. '%H-7A ~ NA Rubber frmea. N/A Aspiaced 1-198 N%-200-29 PSAr025 hnp~r type ioed ph. N/A faLhre Aeptaaed 1-199 QW?8-16 PSA-1 AS NA N/A Aspera ed Nlh N/A Qepatwf 1-200 1-201 1-202 C&478-1930 Qr4?8-2'A5
~- a~2200 PSA-\.00 PSA-5AS PSA-5.00 Bearing cbaraae NA Sg4arlcalbearh94slodged.
N/A N/A
~ ANre drag Aspiaced Aspired 5-204 BF4$ %9010 SP-30.00 Paddle/dsrnp eatect.~. N/A N/A Qephmd 1-215 N~ 9-284 IP-70AS Paddle/cleep cwhct. mao. Qeptaced 1-217 i&I~1 PSA2S NA N/A Ngh drag faQF0 Replaced 1-218 3~01 ~)2$ NA SNNxI'thm. N/A 1-219 1-220 CH-25~9 CH-2ZHf10 1-RQ AC-1&F1 pSH)25
~50 PSA&50 NA NA NA'A Snubber frozen. M/A Ngb ~~
Ngh drag faBee N/A 1-225 RC-24Rll
~
PQIr450 Snnkber Orozco.
1-22? RC-24&44 1-228 ~lfC-247%
1-2294IC<4?~
PS'5 PSH)25 PSH)25 NA Ape chmp bose.
Pfpe clamp loose. .
Sacker Oetn.
Offtlcultto ~
Free 4rhg stroke N/A
~
il/A drag Aepleced Aepleced Qephoed 1-2304RC-24?~ PSA25 Padde beat, ln centmtwlO dev}s. Froze durity stretto N/A Qep4aed 1-231 "fRCSV-l3 PSA<2S NA St&be lb'. N/A Qep baaed 1-234 ACSV-22 PS&426 Loed Cef leyreplily haMed. N/A N/h Qe paired
)-255: RC6V-25 PSk425 NA N/h Ngb drag faire Qepleoed 1-236 7S>>Oia ~25 Nh SxQwr Oaten. NlA Rep~
1-FJ? Sl"101-13 ~25 NA N/A ~ Nag A%re Rgdaced 1-240'P!W57 ~.00 NA 8/h Exceeded AQy Aepteced
ISOME'IRIC NO. FIG-1-9 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEH REACTOR VESSEL ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEH COMPONENT COHPONENT CODE ITM CODE EXAMINATION EXAM DATA SET.
NUHBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS LUG-01 CSB-L-1 CSB LUG 1 9 30 deg. B13. 30 B-N-2 VT-3 IS I-072 X 072-1 ACCEPTABLE LUG-02 CSB-L-2 CSB LUG 2 9 70 deg. B13. 30 B-N-2 VT-3 ISI-072 X 072-9 ACCEPTABLE LUG-03 CSB-L-3 CSB LUG 3 9 110 deg. B13.30 B-N-2 VT-3 ISI-072 X 072-8 ACCEPTABLE LUG-04 CSB-L-4 CSB LUG 4 9 150 deg. B13.30 B-N-2 VT-3 ISI-072 X 072-5 ACCEPTABLE LUG-05 CSB-L-5 CSB LUG 5 0 190 deg. B13.30 B-N-2 VT-3 ISI-072 X 072-6 ACCEPTABLE LUG-06 CSB-L-6 CSB LUG 6 9 230 deg. B13.30 B-N-2 VT-3 ISI-072 X 072-7 ACCEPTABJ E LUG-07 CSB-L-7 CSB LUG 7 6 270 deg. B13.30 B-N-2 VT-3 ISI-072 X 072-4 ACCEPTABLE LUG-08 CSB-L-8 CSB LUG 8 9 310 deg. B13.30 B-N-2 VT-3 ISI-072 072-3,6 10 BURR 8 BOTTOM OF LUG LUG-09 CSB-L-9 CSB LUG 9 6 350 deg. B13.30 B-N-2 VT-3 ISI-072 X 072-2 ACCEPTABLE
TEST PACKAGE NO. 1-IPT-02 ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 'Tue Aor 22 1986 SYSTEM SIS INSTRUMENTED INSPECTION TECHNIQUE IIT H A.F.A DESIGN 24b5 PSIG 650 Beg e IDENTIFICATION LOOP 1Al SIS 1985 PRESSURE TEST
SUMMARY
REPORT EXAMINATION TABLES TEST 1450 PSIG AMB . deg ITEM LINE DESCRIPTION CODE ITM CODE EXAMINATION TEST PROC DATA SHT CLASS HOLD NO. NUMBER NUMBER CATEGORY METHOD NUMBER NRI . RI GEO OTHER 'NUMBER TIME ITT-7 12-SI-102 TO V-3225 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-8 12-SI-148 TO V-3227 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-9 6-SI-112 TO PEN NO. 37 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-10 6-SI-112 , FROM P-37 TO V3124 B15.51 B-P VT-2 12.8 1-IPT-02 12.8.1 2 HRS ITT-11 SEE DESC. 3-SI-139 & 2-SI-132 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-13 2-SI-132 TO HCV-3626 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-14 2-SI-272 TO HCV-3627 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-15 N/A LINES LESS THAN 2" B15 51 B-P VT-2 12.8 1-IPT-02 -X 12.8-1 2s ITT-16 N/A OUTSIDE EXAM BONUND C7.40 C-H VT-2 12. 8 1-IPT-02 12.8-1 ITT-18 12-SI-101 TO V-3215 B15.51 B-P VT-2 12. 8 1-IPT-02 X 12.8-1 2 HRS ITT-19 12-SI-149 TO V-3217 B15.51 B-P VT-2 12. 8 1-IPT-02 ,
X 12.8-1 2 HRS ITT-20 6-SI-113 TO PEN NO 36 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-21 6-SI-113 FROM P-36 TO V-3114 B15.51 B-P 'T-2 12.8 1-IPT-02 12.8-1 2 HRS ITT-22 SEE DESC 3-SI-140 & 2-SI"126 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-24 2-SI-131 TO HCV-3616 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-25 2-SI-271 TO HCV-3617. B15.51 B-P VT-2 12.8 1-IPT"02 X 12.8-1 2 HRS ITT-27 N/A VENT, DRAIN, INST. B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-1 2 HRS ITT-28 N/A OUTSIDE EXAM BOUND C7.40 C-H VT-2 12.8 1-IPT-02 12.8-1 2 HRS ITT-30 12-SI-103 TO V-3235 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-31 12-SI-150 TO V-3237 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-32 6-SI-111 TO PEN NO. 38 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-33 6"SI-ill FROM P-38 TO V-3134 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-34 SEE DESC 3-SI-138 & 2-SI-145 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-36 2-SI-237 TO HCV-3637 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-37 2-SI-133 TO HCV-3636 B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-38 N/A VENT, DRAIN, INST B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-39 N/A OUTSIDE EXAM BOUND C7.40 C-H VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-40 N/A VENT, DRAIN, INST. B15.51 B-P VT-2 12.8 1-IPT-02 X 12.8-2 2 HRS ITT-41 N/A OUTSIDE EXAM BOUND C7.40 C-H VT-2 12.8 1-IPT-02 X 12.8-2
TEST PACKAGE NO. 1-IPT-04 ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 Tue Apr 22 1986 SYSTEM . CVCS INSTRUMENTED INSPECTION TECHNIQUE IIT H.A.P-A DESIGN 2485 PSIG 650 deg.
IDENTIPICATION LETDOWN IN.CTMT 1985 PRESSURE TEST
SUMMARY
REPORT EXAMINATION TABLES TEST 2235 PSIG AMB
- deg ITEM LINE DESCRIPTION CODE ITM CODE EXAMINATION EXAM TEST PROC DATA SHT. CLASS HOLD NO. NUMBER NUMBER CATEGORY METHOD PROC. NUMBER NR I RI GEO OTHER . NUMBER TIME ITT-1 2-CH-100 RGX & V2516 TO P-26 C7.40 C-H VT-2 12. 8 1-IPT"04 X 12.8-3 2 2 HRS ITT-2 2-CH-103 RGX & V2516 TO P-26 C7.40 C-H VT-2. 12. 8 1-IPT-04 X 12.8-3 2 2 HRS ITT-3 2-CH-103 P-26 TO V2342 & 2344 C7.40 C-H VT-2 12. 8 1-IPT-04 X 12.8-3 2 2 HRS ITT-4 2-CH-128 P-26 TO U2342 & 2344 C7.40 C-H UT-2 12. 8 1-IPT-04 X 12.8-3 2 2 HRS ITT-5 2-CH-143 P-26 TO V2342 & 2344 C7.40 C-H VT-2 12. 8 1-IPT-04 X 12.8-3 2 2 HRS ITT-6 2-CH-142 P-26 TO V2342 & 2344 C7.40 C-H VT-2 12. 8 1-IPT-04 X 12 '-3 2 2 HRS
TEST PACKAGE NO. 1-IPT-05 ST. LUCIE NUCLEAR POWER Pf ANT, UNIT NO. 1 Tue Apr 22 1986 SYSTEM CH PUMP SUCTION INS'IRUMENTED INSPECTION TECHNIQUE IIT H.A. P.A DESIGN 200 PSIG 200 deg o IDENTIPICATION CHARGING PUMP 1985 PRESSURE TEST
SUMMARY
REPORT EXAMINATION TABf ES TEST 130 PSIG AMB deg ITEM LINE DESCRIPTION CODE ITM CODE EXAMINATION EXAM TEST PROC DATA SHT CLASS HOLD NO. NUMBER NUMBER CATEGORY METHOD PROC NUMBER NR I RI GEO OTHER NUMBER TIME ITT-42 3-CH-937 PROM V2509 TO V2508 Cj. 40 C-H VT-2 12. 8 1-IPT-05 X 12.8-4 2 2 HRS ITT-43 3/4-CH-962 TO V-2877 C7.40 C-H VT-2 12. 8 1-IPT-05 X 12.8-4 2 HRS ITT-44 3-CH-939 TO V-2190 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 2 HRS ITT-45 SEE DESC 3-CH-944 6 4-CH-544 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-47 4-CH-368 TO V-2118 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-48 3-CH-801 TO V-2514 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-49 1.5-CH-558 TO V-2180 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-50 1/2-CH-957 TO V-2311 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-51 ITT-52 1-CH-A15 3/4-CH-A41 TO V-2174 TO V-2845 C7.40 C7.40 C-H C-H VT"2 VT-2 12.8 12.8 1-IPT-05 1-IPT-05 X
X
- 12. 8-4 12.8-4 +S ITT-53 1/2-CH-966 TO V-2308, C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-54 1/2"CH-194 TO V-2838 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-55 3-CH-593 TO V-2191 C7.40 C-H VT-2 12.8 1-IPT-Q5 X 12 ~ 8" 4 2 HRS ITT-56 1-CH-193 TO V-2837 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-57 4-CH-967 TO V-2316 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-58 2-CH-532 TO V-2326 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-59 1/2-CH-534 TO V-2315 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-60 1/2"CH-381 TO V-255Q C7.40 C"H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-61 1/2-CH-536 TO V-2437 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-62 1/2-CH-535 TO V-2317 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-63 4-CH-947 TO CHG. PUMP 1B C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-64 2-CH-538 TO V-2325 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-65 1/2-CH-948 TO V-231& C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-66 1/2-CH-382 TO V-2551 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-67 1/2-CH-541 TO V-2438 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-68 1/2"CH"540 TO V-2320 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-69 4-CH-368 TO V-2322 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS ITT-70 2-CH-543 TO V-2324 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS-ITT-71 1/2-CH-542 TO V-2321 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 ITT-72 1/2-CH-382 TO V-2552 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 ITT-73 1/2-CH-545 TO V-2323 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 ITT-74 1/2"CH-546 TO V-2439 C7.40 C-H VT-2 12.8 1-IPT-05 X 12.8-4 2 HRS
TEST PACKAGE NO. 1-IPT-06 ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 Tue Apr 22 1986 SYSTEM CH PUMP DISCHARGE INSTRUMENTED INSPECTION TECHNIQUE - IIT H.A.P.A DESIGN 2735 PSIG 250 deg.
IDENTIFICATION CHARGING PUMP 1985 PRESSURE TEST
SUMMARY
REPORT EXAMINATION TABLES TEST 2335 PSIG AMB deg ITEM LINE DESCRIPTION CODE ITM CODE EXAMINATION EXAM TEST PROC DATA SHT CLASS HOLD NO. NUMBER NUMBER CATEGORY METHOD PROC. NUMBER NRI RI GEO OTHER NUMBER TIME ITT-75 2.5-CH-111 N/A C7.40 C-H VT-2 12.8 1-IP T-06 X 12.8-5 2 2 HRS ITT-76 2-CH-112 TO I-SE-02-02 C7.40 C-H VT-2 12 ' 1-IPT-06 X 12.8-5 2 2 HRS ITT-77 2-CH-125 TO I-SE-02-03 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-78 2-CH-346 TO I-SE-02-04 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-79 2-CH-126 TO I-SE-02-01 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS
~ ITT-80 2-CH-127 TO V>>2435 & V-2434 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-81 2.5-CH-110 TO I-MV-02-2 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-82 2-CH-109 THROUGH PEN. NO. 27 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 ITT-83 2-CH-BOO TO I-MV-02-1 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 ITT-84 2.5-CH-107 N/A C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 ITT-85 2.5-CH-106 N/A C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 ~
2 HRS ITT-86 2-CH-.104 TO VO-2134 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-87 2-CH-135 TO I-V02132 & V-2338 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-88 2-CH-136 TO V-02133 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-89 2-CH-137 TO V-2340 & 2-CH-135 C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-90 N/A VENTtDRAINt INST C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-91 N/A VENT, DRAIN & INST. C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-92 N/A VENT, DRAIN, INST C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-93 I-V02304/2305 VENT, DRAIN, INST. C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-95 V-2818 VENT~DRAIN,INST. C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8"5 2 2 HRS ITT-96 V-2427 VENT,DRAINtINST. C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-97 V-2428 VENTtDRAINtINST C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-98 V-2425 VENT,DRAINgINST. C7.40 C-H VT-2 12.8 1-IPT-06 X 12.8-5 2 2 HRS ITT-99 SEAL TANK OUTSIDE EXAM BOUND C7.40 C-H VT-2 12.8 1-IPT-06 12.8-5 2 2 HRS ITT100 V-2803 OUTSIDE EXAM BOUND C7.40 C-H VT-2 12.8 1-IPT-06 12.8-5 2 2 HRS
TEST PACKAGE NO. 1-IPT-01 ST. LUCIE NUCLEAR POWER Pf ANT, UNIT NO. '1 Tue Apr 22 1986 SYSTEM RCS DESIGN 2485 PSIG 650 deg.
IDENTIFICATION PRI. HYDRO TEST 1985 PRESSURE TEST
SUMMARY
REPORT EXAMINATION TABf ES TEST 2295 PSIG 500 deg ITEM LINE DESCRIPTION CODE ITM CODE EXAMINATION EXAM TEST PROC DATA SHT. CLASS HOLD NO. NUMBER NUMBER CATEGOR Y METHOD PROC. NUMBER NR I RI GEO OTHER NUMBER . TIME HYD-01 30-RC-112 30 RCS PIPING B15 ~ 51 8-P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-02 42-RC-114 HOT LEG B15.51 B-P VT-2 9.9"2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-03 30"RC-115 30" PIPING B15.51 B-P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 lfRS HYD-04 30"RC-121 30" PIPING 815.51 B"P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-05 42-RC-123 HOT LEG PIPING B15.51 B-P VT"2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-06 30-RC-124 30" PIPING B15.51 B-P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-07 4-RC-101 PRESSURIZER RELIEF B15.51 B-P VT-2 9.9-2.1 . 1-IPT-01 X M-85-7486 1 4 HRS HYD-08 4-RC-103 PRESSURIZER SPRAY B15.51 B-P VT-2 9.9-2 ' 1-IPT-01 X M-85-7486 1 4 HRS HYD-09 12"RC-108 PRESSURIZER SURGE 815.51 B"P VT-2 9.9-2.1 1-IPT-01 X M-85-'?486 1 4 HRS HYD-10 12-RC-147 SHUTDOWN COOLING B15.51 B-P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-11 12"RC-151 12-RC-152,152,154 B15.51 B-P VT-2 9 '-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-12 PRZ ~ RELIEF 2.5-RC-156,157 B15.51 B-P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-13 SEE DESC VENT, DRAIN, INST B15.51 B-P VT-2 9.9",2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-14 3-RC-109, & 141 PRZ SPRAY IINE
~ 815.51 B-P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-15 N/A PRESSURIZER B15.21 B-P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-16 lA & 1B STEAM GENERATOR A&B B15.31 B-P VT-2 9.9-2.1 1-IPT-01 X M-85-7486 1 4 HRS HYD-17 lAl,lA2,181,1B2 RCP PUMPS B15.61 B-P VT-2 9.9"2.1 1-IPT-01 X M-85-7486 1 4 HRS
ISOMETRIC NO. A-09 1985 INSERUICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM PRESSURIZER ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEM COHPON ENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION 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 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM STEAM GENERATOR A ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI 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 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue APr 22 1986 SYSTEM REACTOR COOLANT ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
HUMBER IDEHTIRICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001288 VALVE CV-3217 16 STUDS 6 16 HUTS B6.9 B-G-2 VT-1 9.9-1.1 X M-85-6965 FLANGE LEAKING 001296 MV-3614 12" GATE VALVE BOLT. B6.9 B-G-2 VT-1 9.9-1 1
~ X M-85-6964 M-85-7023i7026
ISOMETRIC NO. A-26 1985 INSERV'ICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM RC ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEM COMPONENT COMPONENT CODE ITH CODE EXAMINATION EXAM DATA SHT-NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001304 VALVE MV-3480 16 STUDS & 16 NUTS B6 ~ 9 B-G-2 VT-1 9.9-1.1 X H-85-6875 001342 VALVE V-1215 4 STUDS 6 4 NUTS B6.9 B-G-2 VT-1 9.9-1.1 X H-85 6966 EVIDENCE OP LEAKING>
ISOMETRIC NO. A-28 1985 IHSERVICE INSPECTION
SUMMARY
REPORT, EXAMINATION TABLES Tue Apr 22 1986 SYSTEM REACTOR COOLANT ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT NUMBER IDEHTIPICATIOH DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER ~ REMARKS 001347 VALVE V-2431 4 STUDS 6 4 NUTS B6.9 B-G-2 VT-1 9.9-1.1 X M-85-7325 BORIC ACID
ISOMEIRIC NO. A-31a 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM CVCS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEN COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD , PROC NRI RI GEO OTHER NUMBER REMARKS 000635 2-CH-145-9PR PIPE RESTRAINT B4.10 B-K-2 VT-3 9.9-3.1 X H-85-7145
ISOHE'IR IC NO. A-34 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM CVCS ST LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEH COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
'NUHBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUHBER REMARKS 001348 VALVE CV-2432 4 STUDS Ec 4 NUTS B6.9 B-G-2 VT-1 9.9-1.1 X H-85-7338 000770 2-CH-148-9PR PIPE RESTRAINT B4.10 B-K-2 VT-3 9.9-3.1 X M-85-7160
I
~ ~ P
ISOMETRIC NO. A-37a 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PI,ANT, UNIT NO. 1 CLASS 1 ITEM COMPONENT COHPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001085 6-SI-112-46PR PIPE RESTRAINT B4. 10 B-K-2 VT-3 9 '-3.1 X '-85-6796 .
~ .g ISOMFIRIC NO. A-38 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PI ANTi UNIT NO. 1 CLASS 1 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001312 VALVE CV-3114 VALVE BOLTING 12 N/B B6.9 B"G-2 VT-1 9.9-1.1 X M-85-6729 HEAVY BORON BUILDUP 001101 6-SI-113-llPR PIPE RESTRAINT B4.5 B-K-2 VT-3 9.9-3.1 X M-85-7020 LOOSE BOLTS
ISOMETRIC NO. A-39/40 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABL ES Tue Apr 22 1986 SYSTEM RCP ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 1 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI 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 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 SYSTEM SHE ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 1986'TEH COMPONENT COMPONENT CODE ITH CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIFICATION DESCRIPTION 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
L ISOMETRIC NO. B-06 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM MS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEH COMPONENT COMPONENT CODE ITM CODE EXAHINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY =-
METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001514 34-MS-28-5PR PIPE RESTRAINT C2.6 C" E-2 VT-3 9.9.-3.1 X M-85-6868 001507 34-HS-28-1PR PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 X H-85"6867 001525 34-HS-28-10PSS PIPE SUPPORT C2.6 C-E-2 VT-3 9.9.-3.1 X M-85-6866
1 a ~
ISOMETRIC NO. B-Q7 1985 INSERVICE INSPECTION SUHHARY REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM MS ST. LUCIS NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER , REMARKS 001541 34-MS-29-5PR PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6858
ISOHBIRIC NO. B-08 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM HFW ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER , REMARKS AUG-Ol 18-BF-51-2A NOZZLE TO SAFE END C5.21 C-F UT 5.16 5.16-1 AUGMENTED EXAM AUG-2 18-BF-51-2B SAFE END TO ELBOW C5.21 C-F UT 5.16 X 5.16-1 AUGMENTED EXAM AUG-3 18-BF-51-3A ELBOW TO PIPE C5 ~ 21 C-F UT 5.16 5.16-1 AUGMENTED EXAM
ISOMETRIC NO. B-09 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM HFW ST. LUCIE NUCLEAR POWER PLANTi UNIT,NO. 1
- CLASS 2 ITEM COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT COMPONENT'DENTIFICATION NUMBER DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER ~ REMARKS AUG-5 18-BF-52-2B SAFE END TO ELBOW C5.21 C-F UT 5.16 X 5.16-1 AUGMENTED EXAM 001611 20-BF-19-6PR PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6859 AUG-3 18-BF-52-2A NOZZLE TO SAFE END C5.21 C-F UT 5.16 X 5.16-1 AUGMENTED EXAM AUG"6 18-BF-52-3A ELBOW TO PIPE C5.21
'-F UT 5.16 X 5.16-1 AUGMENTED EXAM 001621 BFH-76A PIPE RESTRAINT BF-M6 C2.6 C-E-2 VT-3 9.9-3.1 X M"85-6857
ISOMETRIC NO. B-10 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COMPONENT COMPONENT, CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD . PROC NRI RI GEO OTHER NUMBER ~ REMARKS 002175 VALVE V-07-1555 BOLTING 20 STUD,40 N C4.2 C-D VT-1 9.9-1.1'- X H-85-6727 BORON ACCUMULATION
ISOMETRIC NO. B-11 1985 INSERVICE INSPECTION SUMHARY REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 002174 VALUE 07-1555 BOLTING 20 STUD,40 N C4.2 C-D VT-1 9.9-1.1 X M-85-6724 EVIDENCE OF LEAKAGE
SYSTEM CLASS SIS 2
'985 ISOMERIC NO. B-12 INSERVICE INSPECTION SUHHARY REPORT EXAMINATION TABLES ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 Tue Apr 22 1986 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT-NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER . REMARKS 002178 VALVE FCV-3306 VALVE BOLTING C4 ~ 2 C-D VT-1 9.9-1.1 X H"85-6723 40 STUDS, 40 NUTS
ISOMETRIC NO. B-13 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986" SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COHPONENT COMPONENT CODE ITH CODE EXAHINATION EXAM DATA SET.
NUMBER .IDENTIFICATION DESCRIPTION NUMBER CATEGORY - METHOD PROC NRI RI 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 1985 INSERVICE INSPECTION
SUMMARY
REPORT'XAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COMPONENT COHPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI 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 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apz 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIPICATION DESCRIPTION NUHBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001844 12-SI-477-5PR PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6736 REPAIREDN REALIGNED
ISOME'IRIC NO. B-20 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS QQ2181 VALVE V-3206 BOLTING 8 STUDS/NUTS C4.2 C-D " VT-1 9.9-1.1 X M-85-6728 EVIDENCE OP LEAKAGE
SYSTEM CLASS ITEN SIS 2
'985 ISOMETRIC NO. B-21 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 Tue Apr 22 1986 COMPONENT COMPONENT CODE ITH CODE EXAMINATION EXAM DATA SET.
NUHBER IDENTIFICATION -DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001949 10-SI-420-16PR1 PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 M-85-6891 001941 10-SI-420-11PR1 PIPE REST. SIH-223 C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6963 REALIGNED 001926 10-SI-420-11PR1 PIPE RESTRAINT C2.6 C-E-2 .VT-3 9.9-3.1 X H-85-7265 001958 10-SI-420-22PR PIPE RES'IRAINT C2.6 C-E-2 VT-3. 9.9-3.1 X 'M-85-6892
ISOMETRIC NO. B-2la 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEH COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT NUMBER IDENTIPICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 001990 10-SI-420-48PR PIPE RESTRAINT C2. 6. C-E"2 VT-3 9.9-3.1 X H-85-6732 LOOSE WASHERS 001997 10-SI-420-52PR PIPE RESTRAINT C2 ~ 6 C-E-2 VT-3 9.9-3.1 X H-85-6734 HISSING NUTS
ISOMETRIC NO. B-22 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2
'TEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM ~ DATA SHT.
NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 002025 10-SI-422-15PR PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6795 ACCEPT AS-IS 002013 10-SI-422-6PR PIPE RESIRAINT C2.6 C-E-2 'T-3 9.9-3.1 X M-85-6876
ISOME'IRIC NO'. B-22a 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS 2 ITEM COMPONENT COMPONENT CODE ITH CODE EXAMINATION EXAM DATA SHT.
NUHBER IDENTIFICATION DESCRIPTION NUHBER CATEGORY METHOD PROC NRI RI GEO OTHER NUHBER REMARKS 002056 10'-SI-422-39PR1 PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6767 002057 10-SI-422-39PR2 PIPE RESTRAINT C2.6 C-E-2 VT-3 9.9-3.1 X M-85-6769
ISOMETRIC NO. B-23 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 1986 SYSTEM SIS ST- LUCIE NUCLEAR POWER PLANT, UNIT NO 1~
CLASS 2 ITEM COMPONENT COMPONENT CODE ITM CODE EXAMINATION EXAM DATA SHT.
NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NR I R I GEO OTHER NUMBER REMARKS 't 001320 HCV-3615 6 GLOBE VALVE BOLT C4.2 C-D VT-1 9.9-1.1 X M-85-6730 002108 6-SI-409-2PLS (2) SUPPORTS 1 6 2 C2.6 C-E-2 VT-3 9.9-3.1 X '-85-6735 ACCEPT USE AS-IS
ISOMERIC NO. B-24 1985 INSERVICE INSPECTION
SUMMARY
REPORT EXAMINATION TABLES Tue Apr 22 *1986 SYSTEM SIS ST. LUCIE NUCLEAR POWER PLANT, UNIT NO. 1 CLASS . 2 ITEM COMPONENT COMPONENT CODE ITM CODE , .EXAMINATION EXAM DATA SHT, NUMBER IDENTIFICATION DESCRIPTION NUMBER CATEGORY METHOD PROC NRI RI GEO OTHER NUMBER REMARKS 002138 6-SI-462-9PR PIPE RESTRAINT C2.6 C-E-2 VT-3 9-9-3.1 X M-85-6733 002131 6-SI-462-2PR PIPE RESTRAINT SIH96 C2.1 C-E-2 VT-3 9.9-3.1 X M-85-7468 DOES NOT EXIST