IR 05000250/1981014
| ML17341A420 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 07/14/1981 |
| From: | Blake J, Herdt A, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17341A418 | List: |
| References | |
| 50-250-81-14, 50-251-81-14, IEB-80-08, IEB-80-8, NUDOCS 8108040636 | |
| Download: ML17341A420 (12) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTAST., N.W., SUITE 3100 ATLANTA,GEORGIA 30303 Report No. 50-250/81-14 and 50-251/81-14 Licensee:
Florida Power and Light Co.
P. 0.
Box 529100 Miami, FL 33152 Facility Name:
Tur key Point Docket Nos. 50-250 and 50-251 License Nos.
DPR-31 and DPR-41 Inspection at T key oint site near Homestead, Florida Inspector:'. Blak I
Approved by:
A. R. Herdt, Section Chief Engineering Inspection Branch Engineering and Technical Inspection Division ate Signed 7 iPSj Date Signed SUMMARY Inspection on June 23-26, 1981 Areas Inspected I
This routine, unannounced inspection involved 28 inspector-hours onsite in the areas of 1E Bulletin 80-08; Licensee Action on Previous Inspection Findings; Preparations for Unit
Steam Generator Outage; Reactor Vessel 10-year ISI (Unit 3), and Maintenance Welding Activities.
Results Of the five areas inspected, no violations or deviations were identified.
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REPORT DETAILS Persons Contacted Licensee Employees H. E. Yaeger, Site Manager
"J.
K. Hays, Nuclear Plant Manager
- S. M. Feith, Quality Assurance
~R.
E. Tucker, Quality Assurance
- T. Essinger, Quality Assurance
- D. W. Jones', Quality Control
- J. Olsonoski, Maintenance
"M. J. Powell, Maintenance G. Gram, Construction Manager M. Crisler, Construction QA F. Carr, ISI Coordinator Other licensee and contractor employees contacted included ISI Examination Personnel, QA 5 QC technicians.
Other Organizations
" *W. Clayton, Southwest Research Institute (SwRI)
NRC Resident Inspectors
- A. Ignatonis, Resident Inspector
- W. C. Marsh, Resident Inspector
~Attended exit interview Exit Interview The inspection scope and findings were summarized on June 26,,
1981 with those persons indicated in paragraph 1 above.
The inspector discussed the item below and informed the Plant Manager that there was a concern over how much management attention was being placed on correcting problems in the Welding Control Area.
Unresolved Item -50-250,251/81-14-01 Management attention to corrective action in welding control problem areas.
Licensee Action on Previous Inspection Findings (Closed)
Infraction (50-250/76-17-05; 50-251/76-17-05)
Inadequate Weld Rod Storage Procedure.
This item was reinspected and addressed in RII Inspec-tion Report Nos. 77-08 and 77-13.
As stated in RII Report No. 77-13 the
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licensee's procedure for Control of Welding Materials is adequate.
The Inspector reviewed this procedure, Administrati ve Procedure 0190. 63 and discussed the implementation of the procedure with the site QA Represent'a-tives.
Based on the fact that an adequate procedure is in effect this item is closed.
The implementation of the procedure is of continuing concern and is discussed further in Pararaph 5 of this report.
(Closed)
Infraction (50-250/79-04-01; 50-251/79-04-01)
Welding Material Control.
The inspector reviewed the Licensees response to this item of noncompliance.
This item was corrected at the time of the response by proper implementation of the welding control procedure.
(Closed)
Infraction (50-250/80-20-01; 50-251/80-17-01)
Failure to fol low Welding Electrode Procedure Requirements.
The inspector reviewed the licensees response to this item of noncompliance.
The inspector noted that the licensee's QA Audit No.
QAO-PTP-80-'08-305 conducted from July 28 August 4, 1980, addressed the same concerns.
This audit was closed out satisfactorily on March 2, 1981.
Therefore, this item is closed.
A concern about how permanent the corrective action was is discussed in paragraph 5.
(Closed)
Unresolved Item (50-250/79-25-01; 50-251/79-25-01)
Steam Generator Shipping and Storage Arrangement.
This item was concerned with the fact that the licensee's process sheet No.79-012, Rev.
1 "Steam Generator Lower Assembly Receipt, Handling and Storage" showed a Nitrogen purge arrangement while the generators were shipped and stored with a Nitrogen Blanket.
The inspector was informed by the licensee that Process Sheet 79-012 was can-celled and replaced with the instruction to store in accordance with the manufacturer's instructions, which in thi s case included maintenance of the Nitrogen Blanket.
This item is closed.
(Open)
Unresolved Item (50-250/79-25-02; 50-251/79-25-02)
Overexpanded Tubes.
This item concerned the fact that the manufacturer's documentation for the steam generator lower assembly reported some overexpanded and some plugged tubes.
The inspector that opened this item had asked to review the engineering analysis for the acceptance or the reported conditions.
The licensee's steam generator program QA Representative stated that the report was on file in the Licensee's General Office but that he would have a copy forwarded to the site for review during a future inspection.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviation.
New unresolved items identified during this inspection are discussed in paragraph I~
Maintenance Welding As a part of the review of the corrective actions for the previous inspec-tion findings, discussed in Paragraph 3,
the inspe'ctor reviewed the licensee's gA Audit and Surveillance Programs.
The inspector reviewed the last tw'o audits with gA personnel.
The latest audit had been conducted from May 15, 1981 through June 15, 1981 and was still incomplete in that a formal exit interview had not been conducted.
(The Audit Report was unsigned and in draft form.)
This audit, No.
gAO-PTP-81-05-346, contained a significant number of findings in the welding control area.
A review of previous audits showed that Audit No.
gAO-PTP-80-08-305 conducted from July 28, 1980 through August 4, 1980 also contained a
significant number of findings.
The inspector reviewed the audit responses ahd the gA suveillance records wihich documented the corrective actions to the 1980 Audit.
The corrective actions appeared to be compre-hensive and, including procedure changes, took until March 2, 1981 to complete and close out the audit.
After the review of the two audits and the three previous inspection findings the inspector was left with the impression that the licensee's management attention only addressed doing enough to correct identified problems without ensuring that the correction was programmatic enough to withstand personnel changes.
The inspector closed out the inspection items in Paragraph 3 because the specific items addressed had in fact been corrected even though it appears that the program has had a relapse since the corrective action.,
The latest audit (No.
QAO-PTP-81-05-346)
not only described the specific audit findings, it also contained an assesment of the welding program which points out the repeat nature of the findings and expresses the opinion that management attention and training are the two ingredients which appear to be missing from the Turkey Point Welding Program.
The inspector agreed with this assessment and informed'the plant management that their reactions to this audit would be reviewed by the NRC and that a
new unresolved item concerning corrective action would be opened in this report.
This is unresolved item (50-250/81-14-01; 50-251/81-14-01,)
Manage-ment attention to corrective action in welding control problem areas.
Reactor Pressure Vessel (RPV) - Inservi ce Inspection (ISI) (Unit 3)
The Unit
RPV was being ultrasonically inspected by Southwest Research Institute (SwRI).
The inspection program included the inspection require-ments of the 1974
& 75 edition of ASME BKPV Code,Section XI and to the extent practicable the requirements of Draft Regulatory Guide 1. 150,
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"Ultrasonic Testing or Reactor Vessel Welds During Preservice and Inservice Examinations."
(The use of this draft reg.
guide was discussed in a meeting between FLAIL, SwRI and NRC in the Region II offices on June 3, 1981.)
The inspector reviewed the SwRI program and procedures for this inspection.
This review included a review of the SwRI tests comparing static versus dynamic calibration of the test system.
This comparison was necessary because initial and periodic calibrations during vessel inspections are done statically (Transducer Hand held on Calibation Block) while the inspection is dynamic (Transducer mounted on manipulator sweeping the area of interest)
The comparison tests were conducted at SwRI and showed no significant difference between static and dynamic calibrations.
The inspector observed calibration of the equipment on the morning of June 24, 1981 and at the change of inspection crews on the evening of June 24, 1981.
The Inspector observed data collection and data review activities on June 24, and 25, 1981.
There were no violations or deviations noted during this area of inspection.
Steam Generator Repair Program (Units 3 and 4)
The licensee has elected to repair the steam generators in Unit 3 now while the unit is down because of the turbine generator outage.
(This is a change from the original schedule which showed Unit 4 commencing October 1981 and Unit 3 in October 1982.)
Necessary license modifications and NRC approvals were received during the time of this inspection.
The inspector met with FPAL Construction Management and Quality Assurance Personnel, as well as operations scheduling personnel, to review short and long term schedules and preparations for the steam generator repair activi-ties.
There were no violations or deviations noted during. this phase of the inspection.
IE Bulletin 80-08 The inspector reviewed the licensee's response t'o IEB 80-08 Serial L-80-423 dated December 30, 1980.
This response was discussed with the licensee's QA and inspection personnel relative to the status of the Unit 3 penetrations for which records could not be found.
The inspector was informed that all
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of the questions regarding the Unit 3 penetrations except for Penetration No.
32 had been resolved by additional records research.
Penetration No. 32 was scheduled for radiography in the near future.
After completion of this radiography, FPLL will submit the promised update response to the Bulletin.
The Bulletin remains open pending receipt of the additional response and review of the records by RII personne C P
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