ML20101D281
| ML20101D281 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/18/1984 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-998, NUDOCS 8412240004 | |
| Download: ML20101D281 (9) | |
Text
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- j TABLE OF CONTENTS Sections Page 1.0 IFIRODUCTION 1
2.0
SUMMARY
2 ch 1 Test Data Summary Table 4
3.0 DISCUSSION 6
4.0 TEST SEOUENCE 7
5.0 INSTRUMENTATION AND DATA AOUISITION 8
Sensor Location and Volume Fractions Table 9
6.0 TEST METHODS 11 Appendices A.
Description of Bechtel ILRT Computer Program B.
ILRT Stabilization Summary Data C.
ILRT Trend Report D.
IBM Computer ILRT Summary Data: Mass point. Total Time E.
ILRT Plots: Airmass, Temperature. Pressure, Vapor Pressure F.
Verification Test Summary Data G.
ISG Calculation H.
LLRT Summary I.
Callaway Computer ILRT Summary Data J.
Tendon End Anchorage Concrete Inspection Report ch 1 l
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SUMMARY
The containment building integrated leakage rate test (Type A) was success-fully completed meeting all acceptance criteria set torth in the governing documents listed in Section 1.
The test results are reported in accordance with the requirements of 10CFR50, Appendix J,Section V.B.3.
The calculated leakage rates were 0.045 wt% per day using the Mass Point Analysis technique and 0.043 wt% per day using the Total Time Analysis technique.
The 95% upper confidence limits were 0.047 wt% per day for Mass Point and 0.051 wt% per. day for Total Time Analysis techniques. The acceptance criteria of 75% of La is 0.150 wt% per day.
Following completion of the ILRT, a successful verification test was per-formed. The Mass Point calculated leakage rate was 0.228 wt% per day with a lower limit of 0.195 wt% per day and upper limit of 0.295 wt% per day. The Total Time calculated leakage rate was 0.251 wt% per day with a lower limit of 0.193 wt% per day and upper limit of 0.293 wt% per day.
During the ILRT and verification test two independent computer systems were used to calculate leakage. The Callaway plant (BOP) computer was generating data simultaneously with Bechtel's IBM-PC computer. A good agreement was found between the two sets of results. The ILRT results of the IBM and plant computers are shown in Appendices D and K respectively.
Pressurization for ILRT started on January 6, 1984 at 1738. Test pressure was reached at 0355 on January 7,1984. All containment fans were turned
.off and a 4.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> stabilization period followed. The 24-hour leakage rate test started at 0845 on January 7.
The 75% of La allowable leakage rate criteria was met after 7.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> testing, however the test continued for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per procedure. The 4-hour verification test started at 0950 and was comoleted at 1350 on January 8, 1984.
Prior to the test, a surveillance of reactor containment penetrations and isolation valves was performed to meet the requirements of Appendix J to 10CFR50, Sections III D.3.
In addition, a general containment inspection was performed on the accessible surfaces in accordance with Section V. of 10CFR30, Appendix J, before pressurization. No containment damage was found.
During the ILRT the tendon end anchorage area of the surveillance tendons were visually inspected in accordance with the requirements of Regulatory added Guide 1.35, Revision 2, Section C, Paragraph 3.
The tendon end anchorage ch 1 inspection report is included in Appendix J.
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1 Appendix J added Tendon End Anchorage Concrete Inspection Report entire appendix change 1 i
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Appendix J Tendon End Anchorage Concrete Inspection Report
. The requirements of US NRC Regulatory Guide 1.35, Rev. 2, Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures, were satisfied during ILRT.
At ILRT test pressure of 48.1 psig, th~e end anchorages of the following tendons were inspected:
Over the Dome Vertical Tendons Hoop Tendons V-20 5BA 9CB V-35 45BA 22CB V-65 51BA 17AC V-74 26AC The concrete surrounding the bearing plates of all the above tendons was checked for abnormal behavior and cracking.
Minor cracks were observed near the end anchorages for tendons V-35 and V-65.
Cracks observed near the hoop tendons 26AC and 45BA were less than 0.01".
The cracks were present due to earlier repair work, and were not aggravated during containment pressurization to ILRT test pressure.
Spalling observed near the tendon anchorage end was due to repair work done earlier, also, and did not result from containment pressurization.
The inspection results are presented in Table J-1 in this Appendix.
Original data sheets are maintained in plant records.
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Table J-1 Tendon End Anchorage
- Inspection Results Tendon
' End Loose Pop Out Overall Anchorage Cracking Spalling Repair Repair Integrity V-203T No No Yes No Satisfactory V-20GB No Yes No No Satisfactory V-353T No No No No Satisfactory V-353B Yes No No No Satisfactory V-653T No No No No Satisfactory V-653B Yes Yes Yes No Satisfactory V-743T No No No No Satisfactory
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V-74@B No No No No Satisfactory SBA@A No No No No Satisfactory SBA@B No No No No Satisfactory 9CB3L No No No No Satisfactory 9CB3C No No No No Satisfactory 17AC@A No No No No Satisfactory 17ACGC No No No No Satisfactory 22CBGB No No No No Satisfactory 22CB3C No No No No Satiufactory 26AC3A No No No No Satisfactory 26ACGC Yes No No No Satisfactory 45AB3A Yes No No No Satisfactory 45ABGB Yes No No No Satisfactory SlBA3A No No No No Satisfactory 51BA@B No No No No Satisfactory Note: The cracks spalling, and loose repair is attributed to earlier repair work.
T = Top; B = Bottom; A, B, C are buttress designations SU-051 J-2
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Callaway Plant Unit 1 Primary Reactor Containment SIT /ILRT Final Report g
Change Notice No. 1 e
i NOTE: To all recipients of Callaway Plant Unit 1 Primary Reactor Containment Structural Integrity Test and Integrated Leakage Rate Test Final Report. Remove following pages from the final report and insert the attached pages into the report.
Page No.
Description 11 Table of Contents 2
Summary Insert the following pages after Appendix I.
Page No.
Description Appendix J Title Page J-1 Appendix J J-2 Table J-l Af ter making the above insertions, place this change notice in the report as page 111.
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M EECTRIC COMi%NY 1901 Gratiot Street.St. Louis December 18, 1984 Vice President Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555 ULNRC-998
Dear Mr. Denton:
DOCKET NUMBER 50-483 CALLAWAY PLANT, UtlIT 1 CGNTAINMENT STRUCTURAL INTEGRITY TEST &
Reference:
ULNRC-794 Dated April 9, 1984 The referenced letter transmitted the Containment Integrated Leak Rate Test (ILRT) Report.
We are transmitting 5 copies of the addendum to this report for information.
Please follow the instructions in the attachment and update your copies of the ILRT final report.
If there are any questions please contact us.
Very truly yours, Donald F. Schnell EK/kc 4
Madling Address RO Box 149, St. Louis MO 63166
STATE OF MISSOURI )
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Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and
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that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By
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6onald F. S6hnell Vice President Nuclear SUBSCRIBED and sworn to before me this /
day of M 198 k A
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BARBARA J. PFAFF NOTARY PUBUC, STATE OF MISSOURI MY COMMISSION EXPlRES APRIL 22. Is35 ST. LOUIS COUNTY
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Gerald Charnoff, Esq.
h Shaw, Pittman, Potts & Trowbridge o
~1800 M. Street,:N.W.
Washington, D.C.
20036 Nicholas.A.'Petrick Executive l Director I
SNUPPS L
5 Choke Cherry Road Rockville, Maryland. 20850 I~
John H. Ne'isler Callaway Resident Office U.S. Nuclear Regulatory Commission RRil l
Steedman, Missouri 65077 j,
. William Forney I
Division of Projects and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory. Commission i
Region III l
_799 Roosevelt' Road
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l Glen Ellyn, Illinois 60137 i
Bruce Little
'Callaway Resident Office U.S. Nuclear Regulatory Commission RR$1 Steedman, Missouri 65077 e
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Jan Stevens j
office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission i
Mail Stop P-316 7920 Norfolk Avenue Bethesda, MD -20014 l
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