IR 05000250/1980001
| ML17339A698 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/01/1980 |
| From: | Blake J, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17339A697 | List: |
| References | |
| 50-250-80-01, 50-250-80-1, 50-251-80-01, 50-251-80-1, NUDOCS 8003190624 | |
| Download: ML17339A698 (12) | |
Text
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~o Cy UNITEDSTATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 FEB -4 1980 Report Nos. 50-250/80-01 and 50-251/80-01 Licensee:
Florida Power and Light Company 9250 West Flagler Street Miami, Florida 33101 Facility Name: Turkey Point Docket Nos. 50-250 and 50-251 License Nos.
DPR-31 and DPR-41 Inspection at Turkey Point site near Homestead, Florida Inspector:
Ho
.Date Signed A. R. Herdt Date Signed SUMMARY Inspection on January 8-11, 1980 Areas Inspected This routine unannounced inspection involved 27 inspector-hours onsite in the areas of inservice-inspection data review and evaluation; welding and nondestruc-tive testing; IE Bulletin 79-13,'adiography (Unit 3); LP inspection of pressurizer nozzle/safe end welds; eddy current testing and plugging of Unit 3 steam generators.
Results Of the areas inspected, no items of noncompliance or deviations were identified.
, ~
8003 190Q Q
DETAILS 1.
Persons Contacted Licensee Employees
+H. E.. Yaeger, Site Manager-J.
K. Hays, Plant Manager Nuclear
~P
~ J. White, Maintenance Superintendent'E.
F. Baker, QA Construction
- C. J. Baker, Technical Department
>G. Gotch, PRNS - General Office-R. Tucker, QA Operations-T. Essinger, Assistant Manager QAO
- S.
M. Feith, QA Operations J. O'rien, Senior QC Supervisor, Construction S. Jackson, QC Supervisor, Construction Other licensee employees contacted included several QC technicians, security force members, and office personnel.
NRC Resident Inspector
+R. Vogt-Lowell
+Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January ll, 1980, with those persons indicated in Paragraph 1 above.
The inspector highlighted the inspector followup item concerning the records vault and the need for a response to Bulletin 79-13, Rev. 2, Paragraph 2.c.
concerning operability of feedwater supports and snubbers.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
'U 5.
Independent Inspection a
~
Pressurizer Safe-End/Nozzle Welds (Unit-3)
The licensee's QC inspector had just completed a liquid penetrant inspection of the pressurizer safe-end/nozzle welds and adjacent base
"2" materials in response to a Westinghouse letter of December 14, 1979, which updated the status of Rochester Gas and Electric (Ginna Station)
pressurizer nozzle weld cracking problem.
The inspector reviewed the Westinghouse letter, the instructions and procedures used, and the documentation of the results of the inspec-tions.
The following nozzle welds were examined by the licensee:
Weld Nos.
W4A, W7, W6, 1A and 1G.
b.
Steam Generator Eddy Current Inspection The inspector reviewed the results of the eddy current inspection of the Unit 3 steam generators.
This included a review of inspection and plugging procedures, tube sheet maps which showed which tubes were inspected and the listing of tubes which were plugged.
The eddy current inspection included the Regulatory Guide 1.83 required inspections and the Westinghouse gauging program.
The status of the tubes plugged in the Unit 3 steam generators at the time of this inspection was as follows:
Steam Generator Outage Start Tubes Plugged Reg.
Guide Gauging New Bonus>"
Total 3A 3B 3C 573 (17.58$ )
592 (18.160 551 (16.90$ )
1
66
52
640 (19. 63'X)
638 (19.57K)
618 (18.96K)
-Bonus tubes are the result of inadvertently plugging the wrong tube due to mismarking.
During discussions about these results the licensee acknowledged that
mismarked or inadvertently plugged tubes in one generator during one outage was excessive and the verification program prior to plugging would be reviewed.
There were no items of noncompliance or deviations in this area of the inspection.
6.
IE Bulletin Follow-up IE Bulletin 79-13, Feedwater Pipe Cracking (Unit 3)
. ~
The licensee had completed the IE Bulletin required radiography on the feedwater line to containment penetration welds and the piping material area downstream of the auxiliary feedwater to main feedwater connection.
These radiographs were reviewed for compliance with the-IE Bulletin requirements.
The piping material downstream of the auxiliaty feedwater connection involved straight-forward radiographic technique.
The containment
-3-penetration connection involved a special technique under the direction of the FPM Ievel III, because the weld was a heavy fillet weld connecting a
3/8-inch thick ring to the outside surface of the feedwater pipe.
This meant that the weld and base material area of interest varied from 0.640-inch thick at the pipe wall to 2 1/8-inch thick on the OD of the ring.
The radiographs were shot using film packs containing three different speed films (types R, M 6 T).
This combination of'films provided 100/ coverage of the area of interest with one RT exposure.
The review of these radiographs completes the IE:II review of the licensee's radiographic effort on Unit 3 for this bulletin.
The remaining outstanding item for Unit 3 is the visual inspection of the feedwater system piping supports and snubbers to verify operability and conformance to design.
The licensee stated that a review of IE Bulletin 79-14 work and the snubber inspection program would be made to assure that the IE Bulletin inspection requirements would be completed.
In any event, the licensee stated that IE:II would be informed as to the method of completing this requirement.
There were no items of noncompliance or deviations in this area of inspection.
7.
Inservice Inspection (ISI) Data Review and Evaluation.
The ISI for Unit 3 was conducted in accordance with ASME BRPV Code Section XI, 1970 Edition through Winter 1970 Addenda, and the ISI for Unit 4 was conducted in accordance with ASME BSPV Code,Section XI, 1974 Edition through Summer 75 Addenda.
The inspector reviewed the data from the 1979 outages of both Unit 3 and Unit 4 inservice inspections.
(The final reports for these inspections from Southwest Research Institute (SWRI) had been received by the licensee but had not been accepted, pending resolution of discrepancies identified during review by FPSL Power Resource and QA personnel.)
a
~
The inspection data reviewed for Unit 3 included the following:
(1)
Ultrasonic Inspection (UT) of Reactor Pressure Vessel Flange to Upper Shell (2)
UT of Pressurizer Surge Line Safe-End-To-Nozzle.
(3)
(4)
UT of Reactor Coolant Pump C Main Flange Studs.
UT of Safety Injection System 10-inch~ Weld 2, Loop B and Weld 8, I,oop b.
The inspection data reviewed for Unit 4 included the following:
(1)
Mechanized UT of the Reactor Pressure Vessel (RPV)
(2)
Ultrasonic Inspection of RPV Flange to Upper Shell from Stud Hole 819 to 7/40.
(3)
Ultrasonic Inspection of Reactor Coolant Pump B Studs (4)
Liquid Penetrant Inspection of Reactor Coolant Pump B Pump Support Iug.
(5)
Ultrasonic Inspection of the following Class 2 welds.
(a)
6" MS-011 Weld 1 (Main Steam)
(b)
6" MS-042 Weld 1 (Main Steam)
(c)
8" SI-222 Weld 3 (Safety Injection)
(d)
14" AC"12 Weld 2 (Auxiliary Coolant)
The data was reviewed for completeness and compliance with the ASME Code, Plant Technical Specifications, and the ISI Program accepted by the NRC.
As stated earlier in this paragraph the ISI reports have not yet been accepted by the licensee so this review was conducted using the review copy of the reports assigned to the QA organization in conjunction with the raw data set copies in the QA vault.
During the course of the review the personnel in the vault were not able to locate the record copy of the long term Inservice Examination Plan for Unit 4, so once again the QA Office copy was used by the inspector for this review.
The situation with the record vault was discussed with the licensee's ISI Coordinator who promised to review the information on file and ensure that the vault has all required ISI materials stored in a readily retrievable manner.
The status of these records will be identified as inspector follow-up item nos.
50-280/80-01-01 and 50-281/80-01-01.
The fact that the site QA Office maintains a
separate complete ISI file and the ISI Coordinator maintains a
separate complete file in the licensee's General Office mitigated the retrieval problem in the vault.
There were no items of noncompliance or deviations in this area of inspection.
8.
Welding and Nondestructive Inspection
The major modification work involving welding is done by the licensee's construction department with the work being a'c'complished by Bechtel and inspections by FP&L Construction Q The inspector reviewed the FPM procedures for the control of and inspec-tion of welding activities contained in the Construction Quality Control, Quality Instruction Manual.
Procedures reviewed included the following:
QI 9.1 Visual Inspection of Welds QI 9.2 Inspection of Field Welding QI 9 '
Radiographic Inspection QI 9.4 Magnetic Particle Inspection QI 9.5 Liquid Penetrant Inspection QI 9.9 Ultrasonic Inspection The inspector also reviewed the documentation packages
. for two 4-inch welds in feedwater heater 2B system done during recent modification work.
The welds were Field Weld 1 on Drawing FSK-M-159 and Field Weld 1 on Drawing FSK-M-160.
These welds were made and inspected in accordance with the requirements of ANSI B31.1, 1977 Edition.
There were no items of noncompliance or deviations in this area of the inspection.