ML17223A231
| ML17223A231 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 07/17/1989 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17223A232 | List: |
| References | |
| NUDOCS 8907260004 | |
| Download: ML17223A231 (12) | |
Text
Page 1 of 10 FORM NIS-1 OWNERS'REPORI'OR INSERVICE INSPECTIONS As required by the provisions of the ASME CODE BUZZES
- 1. Owner Florida Power & Li t Co. P.O. Box 14000 Juno Beach Fl. 33408
- 2. Plant St. Zucie Nuclear Power Plant P.O. Box 128 Ft.Pierce Fl. 33454
- 3. Plant Unit 2
- 7. ~nents Inspected Manufacturer Manufacturer or installer Sta+ or Nat:ional or Installer Serial No. Provxnce No. Board No REACIOR VESSEL COMBUSTION 71172 N/A N/A ENGINEERING COMBUSTION 71372 N/A N/A ENGINEERING 2A STEAM COMBUSTION 71272-1 N/A N/A GENER QXOR ENGINEERING BYRON JACKSON 741-N-0001 N/A N/A BYRON JACKSON 741-N-0002 N/A N/A REACIOR OOOZANT BYRON JACKSON 741-N-0003 N/A N/A PUMP 2Bl REACXOR OOOZANT BYRON JACKSON 741-N-0004 N/A N/A PUMP 2B2 REACIOR CXOZANT FIDRIDA POWER & ZZNE NOS. ON N/A N/A PIPING IZGHI'O. PAGE 7 OF 10 SAFETY IN3ECTION FIDRIDA POWER & ZZNE NOS. ON N/A N/A PIPING, CZASS 1 IZGHT CO. PAGE 7 OF 10 CKQKING/IZI'IXNN FZDRIDA HNER & LINE NQS. ON N/A N/A PIPING ZZGHT CO. PAGE 7 OF 10 MAIN STEAM FIDRIDK HNER & ZZNE NOS. ON N/A N/A PIPING IXGHZ CO. PAGE 7 OF 10 SAFETY INJECTION FIDRIDA HMK & IZNE NQS. ON N/A N/A PIPING, CZASS 2 IZGHl CO. PAGE 7 OF 10 SHUTDOWN CCOZZNG FIDRIDA HMK & ZZNE NOS. ON N/A N/A PIPING IZGHZ CO. PAGE 7 OF 10 CONTAINMEKZ SPRAY FIQRIDA POWER & IZNE NOS. ON N/A N/A PIPING ZZGHI'O. PAGE 7 OF 10 8 907260004 8907i7 PDR ADOCK 05000389 P PDC Note: Supplemental sheets in form of lists, sketches or drawings,may be t (J) used, provided(l) size is 8 1/2 in. x ll in., (2) Mormation in items 1 through 6 on this report is included on each sheet and (3) each sheet is numbered and the number of sheets is recorded a6 the top of this form.
Page 2 of 10 NIS-1 REPORT (Continued)
- 8. Examination Dates: 2-1-1989 to 4-28-1989
- 9. Inspection Interval: First 10 Year 08-08-83 to 08-07-93.
Second Period 08-08-86 to 08-07-90
- 10. Abstract of Examinations The Inservice Examination of selected Class I and II components and piping systems of Florida Power and Light Company's St.Lucie Plant, Unit 2, was performed during the refueling outage which began on February 1, 1989. This was the second and last outage scheduled for the second inspection period of the First 10-year Interval (Program B).
The components and piping systems examined were selected per the First Ten Year Inspection Plan, which was prepared per the requirements of Section XI of the ASME Code, 1980 Edition, through Winter of 1980 addenda.
Manual ultrasonic, liquid penetrant, magnetic particle, and visual nondestructive techniques were used in the examination of the selected components, piping systems, and their supports.
See attached Summary Tables for complete examination results.
Mechanized ultrasonic techniques were utilized in the examination of the reactor vessel. The examinations were conducted by Southwest Research Institute.
Radiography was used in the examination of the 2B1 Reactor Coolant Pump. Duke Engineering & Services Inc. performed the examinations.
Eddy current examinations were conducted by Combustion Engineer-ing from February 2, 1989 through March 1, 1989 on 2A and 2B Steam Generators. 8203 tubes in steam generator 2A and 8256 tubes in steam generator 2B were examined. See the attached NIS-BB report for the summary of examination results.
Snubber functional testing and visual examinations were conducted in accordance with St. Lucie Unit-2 Plant Technical Specifi-cation 3.7.10 and ASME Section XI. Testing services were supplied by Qualtec Testing Services Inc..
System pressure testing was conducted by the plant to applicable Plant Technical Specifications and procedures. The Instrumented Inspection Technique was used as applicable. A summary of the specific systems tested is included in this report on Page 6.
Page 3 of 10 NIS-1 REPORT (Continued)
- 11. Conditions Noted
- 12. Corrective Measures Recommended and Taken CLASS I REACTOR VESSEL A visual examination was conducted on all accessible areas of the vessel interior including upper guide structure, core barrel, and upper head; code categories B-N-l, B-N-2, and B-N-3.
Mechanized ultrasonic examinations were performed on the vessel circumferential welds, longitudinal welds, and inlet nozzles including nozzle inner radius exams. No rejectable indications were noted.
PRESSURIZER Volumetric (UT) examinations were conducted on the upper shell to head weld, the upper shell longitudinal weld, the lower shell to bottom head weld, and the lower shell longitudinal weld. The support skirt to lower head weld was given a surface examination using magnetic particle. No recordable indications were noted.
Volumetric (UT) examinations were also conducted on four of the five nozzle to upper head welds, including inner radius exams.
No recordable indications were noted.
REACTOR COOLANT PUMPS 2B1 reactor coolant pump was disassembled for maintenance and examined. The pump casing welds were radiographed and the casing interior visually (VT-3) inspected. No recordable indications were noted. The pump casing ligament area, studs, and nuts were visually examined. The studs were also volumetrically (UT) examined in place. No recordable indications were noted. A Visual (VT-3,4) examination was performed on the four pump supports. No rejectable indications were noted.
In accordance with NRC Regulatory Guide 1.14,Flywheel Integrity, the flywheel bore and keyways on all four reactor coolant pumps were volumetrically (UT) examined. No recordable indications were noted.
MAIN REACTOR COOLANT PIPING Surface (MT,PT), and volumetric (UT) examinations were conducted on seven circumferential welds, six longitudinal welds, and two branch connection welds. No rejectable indications were noted.
, J Page 4 of 10 NIS-1 REPORT (Continued)
- 11. Conditions Noted
- 12. Corrective Measures Recommended and Taken CLASS I (Cont.)
MAIN REACTOR COOLANT PIPING In accordance with NRC Bulletin No. 88-11, a visual (VT-3) examination of the entire pressurizer surge line was conducted.
The area of examination included the piping, pipe supports, whip restraints, and anchor bolts. No gross discernable distress or structural damage was noted.
PRES SURI ZER SPRAY PI PING Surface (PT) and Visual (VT-3,4) examinations were conducted as applicable on selected piping welds and supports. A rigid strut I.D. I SPS-237 was identified as misaligned and having loose parts. Further investigation identified the strut as one which was intentionally moved due to maintenance activities. The strut was reinspected when the maintenance activity was complete and found acceptable. No rejectable indications were noted.
SAFETY INJECTION/CHARGING/LETDOWN PIPING Visual, surface, and volumetric examinations were conducted on selected piping welds, valves, and supports. Visual examination revealed incomplete thread engagement on valve V-2515 (one stud/
nut). Per Plant procedures, the bolting was adjusted to meet minimum thread engagement, re-examined, and found acceptable.
CLASS II STEAM GENERATORS (Secondary side)
Volumetric (UT) examinations were performed on the intermediate shell to cone weld and the feedwater nozzle to shell weld of 2A Steam Generator. Surface (MT,PT) examinations were conducted on the feedwater nozzle to shell weld and selected integral attachments. I.D. geometry was noted on the shell weld (UT).
MAIN STEAM Visual(VT-3), surface (MT), and volumetric (UT) examinations were conducted as applicable on selected piping welds, supports and integral attachments. No rejectable indications were noted.
Page 5 of 10 NIS-1 REPORT (Continued)
- 11. Conditions Noted
- 12. Corrective Measures Recommended and Taken SAFETY INJECTION/SHUTDOWN COOLING PIPING Visual, volumetric, and surface examinations were conducted on selected piping welds, valves and supports. No rejectable indica-tions were noted.
SNUBBER EXAMINATION AND TESTING Visual examination (VT-3,4) was conducted on 100% of the Unit's snubber population per Plant Technical Specifications. A total of 105 snubbers were functionally tested. This included the initial 10 4 sample, the second sample was required due to failures, and the testing of previous failures. Complete examination and test results are on file at the Plant. A summary of the functional test results is included with this report.
SYSTEM LEAKAGE/PRESSURE TESTING The system leakage tests and visual (VT-2) examinations of class I systems were performed by the Plant prior to plant startup.The system leakage test was conducted during Reactor Coolant (RCS) overpressure. The pressure testing documented on page 6 of this report includes all testing done from 11/25/87 up to 4/28/89.
All the above conditions were dispositioned in accordance with Plant Procedures.
The Examination Summary Tables included with this Report provide the results for the non-destructive examinations performed and a report on percent of examinations complete as of 6/30/89.
An explanation of the Summary Table format is also included.
Page 6 of 10 NIS-1 REEORT(Continued)
Pressure Testing Summary Report Test No. System Description Method/Type Results 2-IET-36 2-IPZ-42 2-IET-42 A,B, & C 2B DIESEL AUXEIZAIK FEEERAXKR OIL 'IRANSFER PUMP 2A DIESEL OIL TRANSFER PUMP PUMP SUCTION SUCTION SUCTION HYDROSTATIC HYDR!X)TATIC HYDFK8ZATIC
~
TEST SATISFACIORY SATISFACIORY TEST SATISFACIQRY 2-IPZ-46 2A & 2B DIESEL OIL TRANSFER PUMP DISVALUE HYEKKSTKTIC TEST UNSATISFACIORY 2-IPZ 07 RCS SYSTEM ZZAEAGE SYS. LEAEAGE TEST SATISFACIORY CONDITIONS NOZED
'Ihe line initial Hydro.~tie Test 2-DO-23, which ties the 2-IET-46 did not Unit 2 due to a leak in the cross connect system with the. Unit 1 system. 'Ihe affect~ line was isolated and the rest of the system was re-tested with no descrepant conditions noted.
NCR 2-218 was generated to initiate repair of the line. Engineer has.determdned that there are no o isolated. A Hy ility or safety concerns related to operating e unit with this line tic test will be conducted following the repair.
I
Page 7 of 10 NIS-1 REPORT (Continued)
Line numbers for the Piping systems with items examined (NDE) this outage.
CLASS I REACTOR COOLANT SAFETY INJECTION CHARGING/LETDOWN I-30-RC-112 I-12-SI-149 I-2-CH-147 I-30-RC-115 I-12-SI-150 I-2-CH-148 I-30-RC-121 I-10-SI-130 I-30-RC-124 I-12-RC-108 I-12-RC-151 I-3-RC-109 I-3-RC-141 I-2-RC-122 I-2-RC-142 I-2-RC-148 CLASS II MAIN STEAM SHUTDOWN COOLING SAFETY INJECTION (HPSI/LPSI)
I-35.5-MS-1 I-12-SI-406 I-12-SI-103 I-34-MS-29 I-12-SI-412 I-12-SI-164 I-34-MS-28 I-12-SI-414 I-12-SI-410 I-10-SI-362 I-6-SI-112 I-6-SI-129 I-6-SI-213 CONTAINMENT SPRAY I-24-CS-2
Page 8 of 10 NIS-1 REPORT(Continued)
We certify that the statement made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.
Certificate of Authorization No.~N A Expiration Date N A Date Signed Florida Power 6 Li ht Co. By Owner CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and /
Mutual Insurance Com an of Norwood Mass. have inspected the components described in this Owner's Data Report during the period 1 Februar 1989 to 28 A ril 1989 and state that to the best of my knowledge and belief, the owner has performed examinations and taken corrective measures described in this Owner's Data 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 examinations and corrective measures described in this Owner's 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.
Commissions 8 7 r Inspector's Signature National Board, State, Province, and Endorsements
Page 9 of 10 NIS-1 REPORT
- 1. Owner: Florida Power and Liciht Co. 700 Universe Blvd.
Juno Bch.FL.33408
- 2. Plant: St. Lucia Nuclear Power Plant P.O.Box 128 Ft. Pierce FL. 33454 3.Plant Unit: 2 4.Owner Certificate of Authorization ~N A S.Commerical Service Date: 8 Aucuust 1983 6.Unit National Board No. ~N A REPORT NUMBER ORGANIZATION DESCRIPTION OF SERVICES JNS-PSL-200-89 FPL INSERVICE INSPECTION FINAL REPORT FPL EDDY CURRENT EXAMINATION OF STEAM GENERATORS FINAL REPORT FPL SNUBBER VISUAL EXAMINATION AND FUNCTIONAL TESTING FINAL REPORT DUKE REACTOR COOLANT PUMP 2B1 CASING WELD INSPECTION REPORT CE EDDY CURRENT EXAMINATION OF STEAM GENERATORS IR-ISI-128 CE REACTOR PRESSURE VESSEL VISUAL INSERVICE INSPECTION NONDESTRUCTIVE EXAMINATION REPORT Project 2701 SwRI 1989 MECHANIZED INSERVICE EXAMINATION REPORT FOR THE REACTOR PRESSURE VESSEL 2-IPT-07, 2-IPT-42 FPL TEST DOCUMENTATION FOR 2-IPT-36, 2-IPT-46 I
INSERVICE PRESSURE TESTING
Page 10 of 10 FORM NIS-BB OWNERS'ATA REPORT FOR EDDY CURRENT EXAMINATION RESULTS As required by the provisions of the ASME CODE RULES EDDY CURRENT EXAMINATION RESULTS PLANT: St. Lucie Unit 5 2 EXAMINATION DATES: February 9, 1989 Thru March 1, 1989 TOTAL TUBES TUBES TOTAL TOTAL INDICATIONS PLUGGED AS PLUGGED PLUGGED STEAM TUBES PREVENTIVE THIS TUBES GENERATOR INSPECTED 204 39%'04 1004 MAINTENANCE OUTAGE IN S/G 8203 52 13 221 8256 41 162 LOCATION OF INDICATIONS
( 20< 100% )
U BENDS EGGCRATES PARTIAL SUPPORTS TOP OF TUBE SHEET STEAM 1 TO 7 8 AND 9 TO g 1 EGGCRATE GENERATOR DHB to DCB H/L C/L H/L C/L H/L C/L 54 1 2 40 Remarks:
ASR = Adjacent stay rod tube TRS = Tube restriction TBP = To be plugged CERTIFICATION OF RECORD We certify that the statements in this report are correct and the tubes inspected were tested in accordance with the requirements of Section XI of the ASME Code.
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- Fl rid Power & Light Co.
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