IR 05000302/1976021
| ML19308D310 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/29/1976 |
| From: | Jape F, Robert Lewis, Swan W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19308D307 | List: |
| References | |
| 50-302-76-21, NUDOCS 8002270754 | |
| Download: ML19308D310 (6) | |
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UNITED STATES
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'"lCLEAR REGULATORY COMMISSir*N
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REGION il I
E 230 PEACHTRE E STR EET, N.W. SUITE 818
o ATLANTA, GEORGIA 30303
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IE Inspection Report No. 50-302/76-21
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Licensee: Florida Power Corporation 3201 34th Street, South Post Office Box 14042 St. Petersburg, Florida 33733 Facility Name:
Crystal River 3 Docket No.:
50-302 License No.:
CPPR-51 Category:
Location: Crystal River, Florida Type of License: B&W, PWR, 2452 Mwt Type of Inspection:
Special Announced Dates of Inspection: October 31-November 2, 1976
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Dates of Previous Inspection: October 19-22, 1976 Inspector-in-Charge:
W. B. Swan, Reactor Inspector Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch Other Accompanying Personnel: None Principal Inspector:
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/14 F. Jape, Reactor Insg'ect#r Date Reactor Projects Section No. 2 Re or Operations and Nuclear Support Branch
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//"Ii"7b Reviewed:
R. C. Lewis, Chief Date l
Reactor Projects Section No. 2
Reactor Operations and Nuclear Support Branch I
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8002270
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f IE Rpt. No. 50-302/76-21-2-
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SUMMARY OF FINDINGS I.
Enforcement Items There were no items of noncompliance identified during the inspection.
II.
Licensee Action on Previously Identified Enforcement Matters
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Not inspected l
III. New Unresolved Items None IV.
Status of Previously Identified Unresolved Items Not inspected V.
Design Changes None VI.
Unusual Occurrences
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None VII. Other Significant Findings
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i None-VIII. Management Interview A management interview was held on November 2, 1976, with Mr. J. C. Hobbs, Jr., Manager - Generation Testing and Mr. R. S. Dorrie, Quality Engineer.
The findings of the inspection were discussed.
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IE Rpt. No. 50-302/76-21-1-
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DETAILS Prepared.by:
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W. B. Swan,~ Reactor Inspector Date Engineering Support Section No. 1 Reactor Construction and Engin'eering Support Branch Dates of Inspection: October 31 - November 2, 1976
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(c-T. E. Conlon, Chief Date
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Engineering Support Section No. 1 Reactor Construction and Engineering Support Branch
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1.
Individuals Contacted a.
Florida Power Corporation (FPC)
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J. C. Hobbs, Jr. - Manager, Generation Testing E. E. Froats - Manager, Site Surveillance R. S. Dorrie - Quality Engineer W. W. Nisula - Structural Engineer D. B. Black - SIT Test Supervisor
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K. Kitson - SIT Test Supervisor, Night.Shif t (Assigned to FPC by Volt Engineering)
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Contractor Organizations Gilbert Associates Commonwealth Corporation (GAI)
J. C. Herr, P.E.
' Structural Engineer F. L. Moreadith - Supervisor of Technical Services and Project Manager for dome repair M. Wardrop - Lead SIT Engineer R. Shirk - ILRT Engineer c.
Wiss, Janney and Elstner Data Acquisition T. Brown - Data Acquisitor R. Kraust - Data Acquisitor 2.
Scope of Inspection This special inspection was made to inspect completed repair of the containment dome and observation of the structural integrity test (SIT) of the containment.
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IE Rpt. No. 50-302/76-21-2-I
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3.
Dome Repair - Documents Reviewed l
P1'ctaburgh Testing Laboratories reports on compressive tests a.
on concrete cylinders cast during dome placements on October 8,
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12 and 15, 1976 were reviewed. Tests were made after seven
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days of curing and 14 days. Minimum compressive strength of
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a cylinder after seven days was 4320 psi and the average was
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4625 psi. Minimum compressive strength of a cylinder tested
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at 14 days was 5060 and the average was 5310 psi. Design i
required that the repair concrete was to attain a strength of 5000 psi before the containment structural integri':y test (SIT)
could start. The SIT was started on October 31, 1976, two days after proof that the repair concrete had reached 50C0 psi.
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Strain charts were plotted during the SIT. The apex of the dome raised 0.75 inches at the test pressure of 66.3 psig. The predicted rise for the unmodified dome was given in the PSAR as 0.90 inch.
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c.
FPC Drawings:
CR3-S-30713-0, " Dome Repair As-Built of Upper Layer of Tendon Conduit, North Ealf."'
CR-3-S-30714-0, " Dome Repair As-Built of Upper Layer of Tendon Conduit, South Half."
CR-3-S-30733-0, " Dome Repair As-Built of New Top of Concrete Elevations, North Half."
CR3-S-30734-0, " Dome Repair As-Built of New Top of Concrete Elevations, South Half."
' 3-5-30726-0, -30727-0, and -30728-0, " Dome Repair As-Built v
os Concrete Removal of Feather Edge and Steps."
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Dome Repair - Inspection of Completed Repair The top surface of the repair concrete on the dome had been smoothed in some areas by the finishers with a cement sand paste.
Survey data proved that adequate cover exists over the top rebar.
After the containment had been pressurized to 12 psig the inspector made
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a detailed visual inspection of the concrete surface. Barely discernable hairline cracks were detected in the new concrete where
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l it had been white-washed for purposes of visual inspection during l
SIT.
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T IE Rpt. No. 50-302/76-21-3-
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Findings for record review and visual inspection of the dome repair are clear.
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Documents Reviewed for Containment Structural Integrity Test (SIT)
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New Appendix SA to Section 5 of Crystal River 3 Final Safety a.
Analysis Report submitted October 5, 1976.
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Amendment 48 to PSAR, dated 3-16-76, Page 5-71 Section 5.6 Testing, Sub Section 5.6.1, Structural Proof Test and Instrumentation.
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Article CC-6000 structural integrity of concrete containment structures, pages 249 to 253 of ASME Boiler Pressure Vessel Code Section III, division 21975 (ACI STD. 359-74) Code for Concrete Reactor Vessels and Containments.
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FPC Generation Testing shif t assignments for SIT /ILRT testing.
e, FPC CRP Unit 3, Generation Testing Department Test Procedure 7-1-150-1-0, Reactor Building Structural Integrity Test thru Revision 4, dated 10-13-76.
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Computerized stress-strain data taken at specified pressure intervals during the SIT.
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Stress-strain diagrams plotted by test engineers frota data for movements of the dome apex and containment walls. Plottings of incremental pressure increase and decrease to 55 psig were observed.
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NRC Regulatory Guide 1.18, Structural Acceptance Test for Concrete Primary Reactor Containments.
6.
Modification to SIT Procedure During Test Reg. Guide 1.18, the PSAR, and ASME B&PV Code,Section III, division 2, stipulated that the containment should be subjected to an accept-ance test that increases the containment internal pressure in approximately equal pressure increments from atmospheric pressure to at least 1.15 times the containment design pressure and that it should be depressurized in the same number of increments. Measure-ments should be recorded at each pressure level.
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IE Rpt. No. 50-302/76-21-4-
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j The inspector noted that the SIT procedure provided for observa-tions and measurements at atmospheric pressure, crack pattern
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observations and inspection of conditions inside the containment at
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12 psig, crack pattern observations and stress-strain' data record-ing at 35 pois, 55 psig and 66.3 psig, on the pressure increase
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The inspector noted that stress-strain data had been taken and
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plotted at 12 psig on the increase cycle, but was not intended to
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j be taken on the down cycle. After discussion with the manager of
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Generation Testing he approved modification of the procedure to l
require stress-strain data plotting at 12 psig on the down cycle.
This is consistent with the intent of controlling documents.
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Observations During Test
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The inspector observed the taking and plotting of stress-strain
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data and inspected the outer surface of the containment at the 12, 35 and 55 psig increments. 'The plotted data for 66.3 psig were
reviewed.
The plotted strains appeared to correlate well with the predicted values.
The maximum crack opening was measured at 0.015
inch in the latest placement of dome repair concrete. Other cracks in the dome and at the corners of the stressing plates for the dome tendons were hairline only. There were no cracks found in the containment cylinder wall or in the ring girder and transition to
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the dome.
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8.
Acceptance of Dome Repair and SIT Results
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At the exit interview the inspector stated that his findings during this inspection and previous inspections indicate that the dome repair meets requirements and commitments.
Findings during the SIT
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are clear but formal acceptance of test results is up to Licensing
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following evaluatien of the formal report on the SIT.
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