ML17219A328
| ML17219A328 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/23/1987 |
| From: | Woody C FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| L-87-35, NUDOCS 8702020181 | |
| Download: ML17219A328 (6) | |
Text
ACCESSION NBR:
FAC IL'0-335 50-389 AUTH. NANE MOODYiC. O.
RECIP. MANE REGULATORY iFORNATION DISTRIBUTION B
-N (RIDS) 8702020181 DOC. DATE: 87/01/23 NOTARIZED:
NO St.
Lucie Plant>
Unit ii Florida Power 5 Light Co.
St.
Lucie Planti Unit 2i Florida,Powev 5 Light Co.
AUTHOR AFFILIATION Flov ida Powev 5 Light Co.
RECIPIENT AFFILIATION Document Contv ol Branch (Document -Contv ol Desk)
DOCKET ¹ 05000335 05000389
SUBJECT:
Discusses containment integvated leak rate testing. Util aag elect to conduct v educed duration intev gv ated leak v'ate testing to satisfg reguirements of faclities Tech Specs for Type A leak rate testing.
DISTRIBUTION CODE:
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TITLE:
OR Submittal:
Append J Containment Leak Rate Testing NOTES:
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JANUARY 33 1987 L-87-35 U. S. Nuclear Regulatory Commission, Document Control Desk Washington, D. C. 20555 Gentlemen:
Re:
St. Lucie Units I and 2 Docket Nos. 50-335 and 50-389 Containment Inte rated Leak Rate Testin The St. Lucie Unit I
and Unit 2 Technical Specifications each require that containment leakage rates be demonstrated at specified intervals and that they be determined in conformance with the criteria specified in Appendix J of IO CFR 50 using the methods and provisons of ANSI N45.4-I972.
IO CFR 50 additionally states "The method chosen for the initial test shall normally be used for the periodic tests".
ANSI N45.4-I 972 specifies the practices and test requirements for the quantitative determination of leakage rates for containment structures.
The standard provides for one of two acceptable methods for leakage-rate testing:
the Absolute Method and the Reference-Vessel Method.
The choice of either method is left to the testing organization and those responsible for acceptance of the containment structure.
The ANSI standard specifies that, for either method, the leakage-rate test period shall extend to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of retained internal pressure.
However, the standard continues "If it can be demonstrated to the satisfaction of those responsible for the acceptance of the containment structure that the leakage rate can be accurately determined during a shorter test period, the agreed-upon shorter period may be used".
A reduced duration (i.e., less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of retained pressure) integrated Leak Rate Test (ILRT) is described in the Bechtel Topical
- Report, BN-TOP-I, Revision I, "Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants."
This topical report was found acceptable by the staff in a letter dated February 6, 1973 (R. C. DeYoung (AEC) to R. D. Allen (Bechtel)).
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U. S. Nuclear Regulatory Commission L-87-35 Page two Florida Power Bc Light Company (FPL) has conducted reduced duration ILRTs at its Turkey Point Units 3 and 4 using the methodology described in the Bechtel Topical Report.
The summary technical reports of the Reactor Containment Building Integrated Leak Rate Test for the most recent ILRTs using the methodology described in Bechtel Topical Report BN-TOP-I, Revision I, for Turkey Points Units 3 and 4 were submitted in FPL letters L-85-368, dated September 26, I 985 and L-86-262, dated June 29, I 986, respectively.
These Type A tests were successfully completed using the Bechtel methodology.
Both units achieved mass point and total time upper confidence limits well within acceptance criteria.
To date, FPL has conducted only 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duration ILRTs at St. Lucie Units I
and 2.
However, FPL may elect to conduct reduced duration ILRTs to satisfy the requirements of the St. Lucie Units I and 2 Technical Specifications for Type A leak rate testing for the upcoming and future refueling outages.
lfadditional information is required on this topic, please contact us.
Very truly yours, C. O. Woo Group Vice President Nuclear Energy COW/EJW/gp cc:
Dr. J. Nelson Grace, Region II, USNRC USNRC Resident Inspector, St. Lucie Plant EJ W4/002/2
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