ML20211K814
| ML20211K814 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/01/1999 |
| From: | Rich Smith NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NMP1L-1463, NUDOCS 9909080075 | |
| Download: ML20211K814 (2) | |
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NiagarahMohawk' September 1, 1999 NMPIL 1463 U. S. Nuclear Regulatory Commission
- Attn: Document Control Desk Washington, DC 20555 RE:
Nine Mile Point Unit 1 Docket No. 50-220 DPR-63
Subject:
Special Report; Reactor Containment Building Integmted Leak Rate Test Gentlemen:
In accordance with Nine Mile Point Unit 1 (NMP1) Technical Specification 6.9.3.e, Niagara Mohawk Power Corporation is submitting Attachment 1, " Reactor Containment Building Integrated Leak Rate Test." As indicated in the attachment, the testing confirmed that the Technical Specifications 3.3.3/4.3.3 and 6.16 Primary Containment Leakage requirements were satisfactorily met.
Very truly yours, Robert G. Smith Plant Manager - NMPl RGS/KLL/jb Attachment xc:
Mr. H. J. Miller, Regional Administrator, Region I
/
Mr. G. K. Hunegs, NRC Senior Resident Inspector Records Management
,j 9909080075990980
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PDR ADOCK 05000220 P
pyg Nine Mile Point Nuclear Station, RO. Box 63, Lycoming. New York 13093-0063
- 315.343.2110
- www.nimo.com t
y..
SUMMARY
REPORT a
i l
REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST JUNE 1999 1.0 '
Purpose The Integrated Leakage Rate Test (ILRT) was performed to verify that the Primary Containment integrated leakage rate is within the acceptance criteria provided in the Nine Mile Point Unit 1 Technical Specifications 3.3.3/4.3.3 and 6.16, in accordance with 10CFR50, Appendix J. This Summary Report meets the reporting requirements of Nine Mile Point Unit 1 Technical Specification 6.9.3.e.
2.0 Procedure The ILRT was performed in accordance with Procedure N1-TSP-201-001, Revision 4,
" Integrated I2ak Rate Test of Primary Containment Type A Test," which is maintained on file at the facility. The test was performed by pressurizing the containment to accident pressure (35 +0/-1.4 psig) for a minimum of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and then using measured containment pressures and temperatures to determine the air mass rate of change. The Total Time Technique of Bechtel Topical Report, BN-TOP-1, Revision 1,
" Testing Requirements for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants," was used to determine the final results.
3.0 Test Results For Nine Mile Point Unit 1:
"As-Irft" Accentance Criteria <0.75 L; (where 0.75 L; = 1.125 w%/ day)
Calculated "As-Left" 95% Upper Confidence Level (UCL) Leakage Rate Test Result =
0.4865 w%/ day "As-Found" Accentance Criteria < 1.0 L;(where L; = 1.5 w%/ day)
Calculated "As-Found" 95% UCL Leakage Rate Test Result = 1.230 w%/ day 4.0 Performance Summarv l
The 1993 reduced pressure ILRT had an acceptable "As-I2ft" leakage rate of 0.4634 w%/ day. Nine Mile Point Unit I has performed two consecutive periodic ILRTs with a calculated performance leakage rate ofless than 1.0 L, The elapsed time between the two tests was greater than 24 months, and the 1999 test was performed at peak accident pressure. Therefore, in accordance with 10CFR50, Appendix J (Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors), Option B, the frequency for subsequent ILRTs is at least one per 10 years.
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