ML020440419
| ML020440419 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 01/11/2002 |
| From: | Hopkins L Constellation Nuclear |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NMP1L 1637 | |
| Download: ML020440419 (2) | |
Text
P.O. Box 63 Lycoming, New York 13093 0
Constellation Nuclear Nine Mile Point Nuclear Station January 11, 2002 A Member of the NM 1L 163 7 Constellation Energy Group 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:
Secondary Containment Leakage Testing Summary Report Gentlemen:
Nine Mile Point Nuclear Station, LLC (NMPNS) is submitting the attached "Secondary Containment Leakage Testing Summary Report" for Nine Mile Point Unit 1 (NMP 1).
This report covers testing performed in April 2001 during refueling outage number 16 to satisfy the requirements of Section 4.4.1, "Leakage Rate," of the NMIP1 Technical Specifications (TS). As indicated in the report, the leakage rate criteria of TS 4.4.1 were met.
TS 6.9.3.f required this report to be submitted within 3 months after completion of testing, i.e. by July 11, 2001. However, due to the lack of specific procedural guidance, the need for this report was not properly identified. NMPNS has entered this occurrence into its corrective action program.
Very truly yours, Lawrence A. Hopkins Unit 1 Plant General Manager LAHIAA/cld cc:
Mr. H. J. Miller, NRC Regional Administrator, Region I Mr. G. K. Hunegs, NRC Senior Resident Inspector Records Management
ATTACHMENT SECONDARY CONTAINMENT LEAKAGE TESTING
SUMMARY
REPORT APRIL 2001 1.0 PURPOSE To assure the capability of the secondary containment to maintain leakage within allowable limits per Technical Specification (TS) 4.4.1, Leakage Rate.
2.0 PROCEDURE DESCRIPTION These tests were performed using Revision 14 of Surveillance Test Procedure Ni-ST-C5, "Secondary Containment and Reactor Building Emergency Ventilation System Operability Test." This procedure is on file at the facility.
3.0 TEST DATA April 9, 2001
- 11 System April 11, 2001
- 12 System Test Conditions Wind Speed Acceptance Criteria Minimum Required Reactor Building Internal Differential Pressure per Section 4.4.1 and Figure 3.4.1 of the TS Reactor Building Leakage Rate Test Results Reactor Building Internal Differential Pressure Ventilation Flow
-0.275 inches of water 1600 cfm**
or less
-0.30 inches of water 1550 cfmn**
-0.26 inches of water 1600 cfmn**
or less
-0.31 inches of water 1575 cfln**
4.0 EVALUATION These test results demonstrated that the reactor building (secondary containment) leakage rate met the acceptance criteria of Section 4.4.1 and Figure 3.4.1 of the TS.
- miles per hour
- cubic feet per minute 1 of 1 8.5 mph*
3.5 mph*