IR 05000250/1982009
| ML20054D663 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/26/1982 |
| From: | Fiedler R, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20054D652 | List: |
| References | |
| 50-250-82-09, 50-250-82-9, 50-251-82-09, 50-251-82-9, NUDOCS 8204230250 | |
| Download: ML20054D663 (9) | |
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tg UNITED STATES l
NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 3o303 o
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Report Nos. 50-250/82-09 and 50-251/82-09 Licensee:
Florida Power and Light P. O. Box 529100 Miami, FL 33152 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:
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R. L. Fiedler Oate Signed Approved by:
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A/,2_R dk h F. Jape / Se'ction Chief
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Engineering Inspection Q[rdnch /
Date Signed Division of Engineering and Technical Programs SUMMARY Inspection on February 22-25, and March 2-5, 1982 Areas Inspected This routine, unannounced inspection involved 48 inspector-hours on site in the areas of review of preoperational test procedures, witnessing preoperational testing, review of the results of preoperational testing; and a tour of the control room, auxiliary building and the Unit 3 containment building.
Results l
Of the four areas inspected, no violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- H. E. Yaeger, Site Manager
- J. K. Hays, Plant Manager - Nuclear
- R. f. Engimeier, Manager QA
- T. Essinger, Assistant Manager, QA
- J. E. Moore, Startup Superintendent
- S. M. Feith, QA Operations Supervisor Other licensee employees contacted included several operators.
NRC Resident Inspector
- R. Vogt - Lowell
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on February 25 and March 5,1982, with those persons indicated in paragraph I above.
During the exit interview conducted on February 25 the licensee asked if a special report on the results of the test program conducted following the Steam Generator Repair Program was required to be sent to the NRC. The licensee also asked if a supplemental letter de.cribing minor changes to the Inte-grated Startup Test Program discription was required.
The licensee was informed on March 2, 1982, that a special report on the results of the test program following the Steam Generator Repair Program was not required by the NRC. Minor changes to the Integrated Startuo Test Program do not require a supplemental letter, however, if a test or check described in the the Integrated Startup Test Program is deleted, a supplemental letter describing the deletion and a justification for deleting the test or check would be required.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items
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Unresolved items were not identified during this inspection.
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5.
Review of Preoperational The inspector reviewed the approved preoperational procedures to verify the following:
a.
That the procedures had been properly reviewed and approved.
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That acceptance criteria against which the test will be judged are clearly identified.
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The procedure appeared adequate and therefore inspector followup item IFI 250/82-03-01 is considered closed (Closed IFI 250/82-03-01).
6.
Witnessing Preoperational Testing The inspector observed portions of the following preoperational tests.
a.
POP 0802.3 Post SGRP Filling and Venting the Reactor Coolant System b.
POP 0802.1 Post SGRP Reactor Heatup The above tests were observed by the inspector to verify the following:
a.
That a procedure of the appropriate revision was available and in use by test personnel.
b.
That all test prerequisites and initial conditions were met.
c.
That the test was performed as required by the procedure and that changes to the procedure were made in accordance with administrative requirements.
d.
That test coordination was adequate.
There were no violations or deviations identified in this area.
7.
Review of the Results of Preoperational Testing The inspector examined the procedure used and the results obtained from the following preoperational tests.
a.
POP 0800.1 Hot Functional Test Sequence Document b.
POP 0800.8 Post SGRP Primary System Pressure Test c.
POP 0800.9 Steam Generator Thermal Expansion Test d.
POP 0802.1 Post SGRP Reactor Heatup - Cold Condition to Hot Shutdown Condition
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POP 0802.2 Post SGRP Reactor Cooldown - Hot Shutdown to Cold Shutdown Condition f.
POP 0802.3 Post SGRP Filling and Venting the Reactor Coolant System The procedures were reviewed to verify that the test data met acceptance criteria, and that deviations and deficiencies were properly identified and resolved. There were four Deficiency Reports written for testing conducted during the preoperation test program. The licensee committed to resolve all deficiencies in the preoperational test program prior to criticality with the exception of the deficiency reported for setting spring hangers for the feedwater lines which require power operation. The results appeared satis-factory pending satisfactory resolution of the remaining deficiencies.
8.
Tour of the Control Room, Auxiliary Building and the Unit 3 Reactor Building A tour of the accessible areas was conducted to determine by observation that plant conditions and activities were in accordance with applicable requirements. During the exit interview the licensee committed to a QC hold point to verify containment cleanliness prior to the reactor vessel head lift.
The refueling procedures are to be revised, to include a QC hold point to verify containment cleanliness prior to the reactor vessel head lift, prior to the next refueling. This is an inspection followup item (IFI 250/82-09-01).