L-91-348, Forwards Listed Inservice Insp Repts,Per ASME Code,Section XI,(IWA-6230)
| ML17348B316 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 12/30/1991 |
| From: | Plunkett T FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-91-348, NUDOCS 9201070255 | |
| Download: ML17348B316 (23) | |
Text
ACCELERATED DIS UTION DEMONST TION SYSTEM
~ ~ ~
REGULATORY INFORMATXON DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9201070255 DOC.DATE: 91/12/30 NOTARIZED:
NO FACIL:50-250 Turkey Point Plant, Unit 3, Florida Power and Light C AUTH.NAME AUTHOR AFFXLXATXON PLUNKETT,T.F.
Florida Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 05000250
SUBJECT:
Forwards listed inservice insp repts,per ASME Code, Section XIi ( IWA 6230)
DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTR ENCL 2 SIZE TITLE: OR Submittal: Inservice Inspection/Testing/Relic from ASME Code NOTES:
D RECIPIENT ID CODE/NAME PD2-2 LA AULUCK,R INTERNAL: NRR/DET/ECMB 9H NUDOCS-ABSTRACT OGC/HDS3 RES/DS XR/EXB EXTERNAL EGGG BROWNi B NRC PDR COPIES LTTR ENCL 1
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NOTE TO ALL"RIDS" RECIPIENTS:
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PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 15 ENCL 12
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P.O. Box 029100, Miami, FL, 33102-9100 PIPll L-91-348 10 CFR 50.55a U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
Re:
Turkey Point Unit 3 Docket No. 50-250 Inservice Ins ection Re ort ASME Code,Section XI, (IWA-6230) requires that Inservice Inspection (ISI) Summary Reports be submitted within 90 days of completion of ISI conducted during a refueling outage.
Please find attached the reports listed below, in accordance with the provisions of this requirement.
Form NIS-1 Owners'ata Report for Inservice Inspections.
Form NIS-BB Owners'ata Report of Eddy Current Examinations.
Form NIS-2 Owners'ata Report of Repairs and Replacements.
Summary of Visual Examinations and Functional Testing of Snubbers.
Summary of Inservice Inspection Examinations.
Should there be any questions concerning this report, please contact us.
Very truly yours, 7;/
Pso~/ceCe
/y T. F. Plunkett Vice President Turkey Point Nuclear TFP/GS attachment cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 920i070255 9ii230 PDR AGOCK 05000250
%i iQ PDR an FPL Group company
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FORM NIS-1 OWNERS'ATA REPORT FOR INSERVICE INSPECTIONS As required by the Provisions of the ASME Code Rules Page 1 of 11 Owner:
Florida Power and Light Company, 700 Universe Blvd-.
Juno
- Beach, Florida 33408 2.
Plant:
Turkey Point Nuclear Power Plant, P.O.
Box 3088, Florida City, Florida
. 33034 3.
4.
5.
6.
7.
Plant Unit:
3 Owner Certificate of Authorization (if required)
~N A Commercial Service Date December 14 1972 National Board Number for Unit:
~N A Components Inspected:
Component or Appurtenance Manufacturer Manufacturer or Installer or Installer Serial No.
State or Province No.
National Board No.
Reactor Pressure Vessel Babcock and Wilcox 610-0116 3PSRV1 N/A N-160 Pressurizer Steam Generator A
Regenerative Heat Exchanger Reactor Coolant Pump A
Reactor Coolant Pump B
Reactor Coolant Pump C
Westinghouse 16A-5883 3T200 Westinghouse 16A-5885-1 FSGT-3001 3E210A Westinghouse 16A-5885-2 FSGT-3002 3E210B Westinghouse 16A-5885-3 FSGT-3003 3E210C Westinghouse 3E200 Westinghouse 3P200A Westinghouse 3P200B Westinghouse 3P200C N/A N/A N/A N/A N/A N/A N/A N/A N-720 N-740 N-742 N-744 N/A N/A N/A N/A Reactor Coolant Piping Bechtel See line nos.
on page 9 of ll N/A N/A
4
~
t"
NIS-1 Report (continued)
Page 2 of 11 Component or Appurtenance Residual Heat Removal Piping Safety Injection Piping Chemical and Volume Control Piping Containment Spray Piping Main Steam Piping Steam Generator Blowdown Piping Feedwater Piping Component Cooling Piping Auxiliary Feedwater Piping Intake Cooling Water Piping Manufacturer or Installer Bechtel Bechtel Bechtel Bechtel Bechtel Bechtel Bechtel Bechtel Bechtel Bechtel Manufacturer or Installer Serial No.
See line nos.
on page 9 of 11 See line nos.
on page 9 of 11 See line nos.
on page 9 of ll See line nos.
on page 9 of 11 See line nos.
on page 9 of 11 See line nos.
on page 9 of 11 See line nos.
on page 9 of 11 See line nos.
on page 9 of 11 See line nos.
on page 9 of 11 See line nos.
on page 9 of 11 State or Province No.
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A National Board No.
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A'
ii
NIS-1 Report (continued)
Page 3 of 11 10.
Abstract of examinations and statement.
concerning status of work required for current interval:
The Inservice Examination of selecte'd Class 1 and 2 components and piping systems of Florida Power and Light's Turkey Point Unit 3 was performed during the Emergency Diesel Addition Outage.
This outage began on December 11, 1990 and ended on October 1, 1991.
This was the first outage of the third period and the fifth outage of the second ten year interval.
The components and piping systems examined were selected per the Second Ten Year Inspection Plan, which was prepared in accordance with the requirements of the 1980 Edition of ASME Section XI with addenda through Winter 1981.
Manual and Mechanized ultrasonic,
- visual, magnetic particle, and l'd netrant non-destructive techniques were used to examine nual the components,
- piping, and their supports.
The Manua examinations were performed by FP&L personnel, supported by examiners supplied by Ebasco Services Inc.
The RPV Internal examinations were performed by Westinghouse Energy Systems personnel, with FP&L personnel reviewing the work performed.
The RPV Mechanized examinations were conducted by Southwest Research Institute.
Edd Current examinations were conducted by FP&L personnel from April 6, 1991 through June 6, 1991 on Steam Generators A, B, and C.
y A total of 9,598 tubes were examined.
See the attached NIS-BB report for the summary of examination results.
The augmented Feedwater Nozzle examination program was conducted during this outage on all three Steam Generators.
The entire area from the nozzle ramp to a point one pipe diameter out on the far side of the elbow was examined with ultrasonics.
Snubber functional testing and visual examinations were conducted in accordance with Turkey Pt. Unit 3 Plant technical specifications and Section XI.
Examination and testing services were supplied by Qualtech Testing Services Inc.
System Pressure testing was conducted by the plant to applicable Plant Technical Specifications and Procedures and Section XI.
The number of examinations performed during this outage and the cumulative total of exams exceed the requirements of Program B of ASME Section XI.
NIS-1 Report (continued)
Page 4 of 11 11.
Abstract of Conditions Noted 12.
Abstract of Corrective Measures Recommended and Taken Class 1
Reactor Pressure Vessel A full RPV examination was conducted using mechanized Ultrasonic and remote Visual methods.
These examinations did not locate any unacceptable flaws.
A mechanically created gouge was seen on the RPV Head Seal Surface.
This gouge has not changed since its discovery.
The examinations covered the vessel circumferential welds, all nozzle to safe-end
- head, and one-third of the RPV closure head
- studs, nuts, and washers.
The flange to dome weld on the closure head had several linear surface indications on the outside surface which were removed by grinding.
An engineering evaluation accepted the resulting cavity to be used as-is.
During installation, two RPV Closure Head studs were damaged.
New studs were examined for replacements, and several additional new studs were examined in case further replacements became necessary.
Steam Generators The supports for Steam Generator C were examined.
No unacceptable conditions were noted.
Pressurizer The pressurizer support
- skirt, one circumferential and one longitudinal weld, and the safety nozzle inner radius were examined using Ultrasonic, Licpxid Penetrant, Magnetic Particle, and Visual examination methods.
No unacceptable conditions were noted.
Reactor Coolant Pumps Reactor Coolant Pump A studs, nuts, flywheel, integral attachments, and pump supports were examined.
No reportable indications were detected.
Reactor Coolant Pump B studs, nuts, flywheel, integral attachments, and pump supports were examined.
One unacceptable linear indication was detected on one of the integral attachments, and
NIS-1 Report (continued)
Page 5 of 11 subsequently removed.
No other reportable indications were detected.
Reactor Coolant Pump C
casing
- welds, studs, attachments, and pump supports were examined.
indications were detected.'uts, integral No reportable Reactor Coolant Piping Surface and volumetric examinations using Liquid Penetrant and Ultrasonic methods were conducted on selected welds.
Acceptable surface and geometric indications were detected.
No unacceptable conditions were noted.
Valve and flange bolting were examined.
Boric acid crystals were found on numerous areas.
These were
- cleaned, in some
- cases, replaced at the option of the maintenance
- crews, and re-examined.
No unacceptable conditions were noted.
Visual examinations were performed on component supports.
No unacceptable conditions were noted.
During the Outage, the RTD lines were removed and the short section of piping that remained was capped.
Baseline examinations were performed on the new welds.
Pressurizer Surge Piping The surge line was examined for movement in accordance with IE Notice 88-11.
Evidence of movement was detected (crushed insulation noted.)
An engineering evaluation of the line determined that this was acceptable, as the movement was expected and essentially the same as previous examinations.
Residual Heat Removal Piping Surface and volumetric examinations using Liquid 'Penetrant and Ultrasonic methods were conducted on selected welds.
Acceptable surface and geometric indications were detected.
No unacceptable conditions were noted.
Visual examinations were performed. on component supports.
Several drawing discr'epancies were noted.
These are being updated as part of the system walkdown and drawing reconstitution effort currently being performed at Turkey Point.
Other problems identified included bent rods,. painted scales, and broken grout.
These were
NIS-1 Report (continued)
Page 6 of ll accepted as-is or cleaned.
None of these indications affected the functionality of the supports.
Safety Injection Piping Surface and volumetric examinations using Liquid Penetrant and Ultrasonic methods were conducted on selected welds.
Acceptable surface and geometric indications were detected.
No unacceptable conditions were noted.
II Visual examinations on the interior surface of two valves was performed.
A nick was detected on one valVe body seat.
Subsequent pressure testing showed that the valve did not leak and the indication was accepted as-is.
Visual examinations were performed on component supports.
One spring hanger was found to be non-function due to mechanical damaged from an outside source not related to inservice use.
This spring can was replaced and additional examinations were performed on the line to determine if other supports may have been damaged.
No other unacceptable conditions were noted.
Chemical and Volume Control Piping Surface examinations were performed on selected welds.
No unacceptable indications were noted.
Visual examinations were performed on selected supports and flange bolting.
No unacceptable indications were noted.
Class 2
Steam Generators The "CL" weld on steam generator C (transition cone to upper shell) was examined.
This examination was performed as part of an ongoing program by PPL to monitor this weld in the Turkey Point Steam Generators.
This is due to concern with cracking that has been detected in this weld at other plants.
Acceptable pitting and slag inclusions were detected.
Residual Heat Removal Piping Visual examinations were performed on selected supports.
Drawing discrepancies were noted.
Load scales on spring cans were painted and needed
- cleaning, inadequate thread engagement and paint on
NIS-1 Report (continued)
Page 7 of 11 spherical bearings was noted.
These were accepted as-is or cleaned.
No unacceptable conditions were found.
Safety Injection Piping Selected welds were examined by liquid penetrant techniques.
Acceptable indications were noted on 1 weld.
An unacceptable indication was found on 1 weld.
After an evaluation, it was determined to be a surface lap caused during the manufacturing process.
No other indications were detected.
Containment Spray Piping Visual examinations were performed on selected supports.
Drawing discrepancies were noted.
No unacceptable conditions were found.
Main Steam Piping Magnetic
- Particle, Penetrant, Ultrasonic, and Radiographic examinations were performed.
Acceptable slag and porosity were detected in 1 weld.
No unacceptable indications were noted.
Steam Generator Blowdown Piping Magnetic Particle and Ultrasonic examinations were performed on selected welds.
One linear indication was detected.
The evaluation determined it to be a surface scratch.
No unacceptable indications were detected.
Visual examinations were performed on selected supports.
Loose nuts were detected on 1 support, which were subsequently tightened.
Incomplete thread engagement was found on 1 support.
This was accepted as-is by engineering evaluation.
One support was examined due to the failure of an adjacent snubber.
Main Feedwater Piping An augmented examination was performed on all three feedwater piping systems.
This consisted on an ultrasonic exam on the piping from the bottom of the Steam Generator nozzle ramp to one pipe diameter upstream of the first elbow to pipe weld.
No indications were detected.
NIS-1 Report (continued)
Page 8 of 11 Magnetic Particle and Ultrasonic'xaminations were performed on selected welds.
Geometric indications were detected.
No unacceptable indications were found.
'E
NIS-'1 Report (continued)
Page 9 of 11 7.
Components Inspected:
Line numbers for the Piping systems examined this outage.
Class 1
REACTOR COOLANT 31>>-RCS-1301 29>>-RCS-1304 2>>-RCS-1307 10n-RCS-1307 3>>-RCS-1307 27.5>>-RCS-1307 31't-RCS-1302 29>>-RCS-1305 2>>-RCS-1306 27.5>>-RCS-1306 31't-RCS-1303 29>>-RCS-1308 27.5>>-RCS-1309 14n-RC-1302 12 n-RC-1301 4 tt RC 1301 4>>-RC-1302 4>>-RC-1303 4>>-RC-1304 REACTOR COOLANT (CONT) 4>>-RC-1305 4>>-RC-1306 3tt-RC-1304 2>>-RC-1301 2>>-RC-1302 2>>-RC-1303 2it RC 1310 RESIDUAL HEAT REMOVAL 14>>-RHR-1301 8"-RHR-1301 8>>-RHR-1302 CHEMICAL AND VOLUME CONTROL 3>>-CH-1301 3 n-CH-1302 2>>-CH-1301 1.5>>-CH-1301 2>>-CH-1304 2>>-CH-1306 SAFETY INJECTION 10>>-SI-1301 10>>-SI-1302 10it SI 1303 2>>-SI-1301 2 it SI 1302 2>>-SI-1303 2>>-SI-1305 2>>-SI-1306 Class 2
SAFETY INJECTION 16>>-SI-2301 10>>-SI-2302 10't SI 2303 8't-SI-2302 RESIDUAL HEAT REMOVAL 14it RHR 2301 10>>-RHR-2303 8>>-SZ-2309 FEEDWATER 14>>-FWA-2302 14it FWB 2303 14 't-FWB-23 05 14it FWC-2306 18"-FWC-2305 6>>-FWB-2302
, 6>>-FWC-2303 STEAM GENERATOR BLOWDOWN 6>>-BDC-2303 6>>-BDC-2306 CONTAINMENT SPRAY 6't-CS-2301 MAIN STEAM 31>>-MSC-2303 26>>-MSC-2303 14 it-MSA-2301 14>>-MSA-2302 26>>-MSC-2306 14>>-MSC-2305 14it MSC 2306
0
NIS-1 Report (continued)
Page 10 of 11 We certify that the statements made in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code,Section XI.
OWNER FLORIDA P ER AN LIGHT COMPANY By:
Date:
I2-I ER FICATE OF AUTHORIZATION NO. (IF APPLICABLE):
N/A IRATION DATE:
N/A CERTIFXCATE 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 DADE COUNTY and employed by ARKWRIGHT MUTUAL INSURANCE COMPANY of NORWOOD, MASSACHUSETTS have inspected the components desc i4yg>jp this OWNERS'ata Report during the knowledge and be 8,>
d Owner has performed examinations and taken corrective measures described in the 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 examinations, and neither the inspector nor his employer shall be liable in any manner for any personal injury or property damage on loss of any kind arising from or connected with this inspection.
~~~~ ~6 Xnsp t
's Signature National Boar
- ate, Province, and Endorsements Date: ~.
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~I NIS-1 Report (continued)
Page ll of 11 1.
Owner: Florida Power and Light Company, 700 Universe Blvd.
Juno Beach Florida 33408 (Name and Address of Owner) 2.
Plant:
TURKEY POINT NUCLEAR POWER PLANT, P.O.
BOX 3088, FLORIDA CITY FLORIDA 33034 (Name and address of Plant) 3 e 4 ~
5.
6.
Plant Unit:
3 Owner Certificate of Authorization (if required)
Commercial Service Date:
December 14 1972 National Board Number for Unit:
~NA
~NA Report Number Organization Description of Services ESI-PTN-3-91 FPL Inservice Inspection Final Report FPL Eddy Current Examination of Steam Generators Final Report Project 3940 SwRI 1990 Inservice Examination of the Reactor Pressure Vessel at Turkey point Plant, Unit 3 Westinghouse Reactor Vessel Internals 40-Month Report, Outage 2-3-1 (1991)
FPL Summary Report of Hydrostatic Testing Program Turkey Point Unit No.
3 1990-91 Diesel Generator Addition Outage FPL Summary Report Visual Examination and Functional Testing of Snubbers