ML032130406
| ML032130406 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/22/2003 |
| From: | Gallagher M AmerGen Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 5928-03-20158 | |
| Download: ML032130406 (3) | |
Text
AmerGen.sm AmerGen Energy Company, LLC www.exeloncorp.com An Exelon/British Energy Company 200 Exelon Way Suite 345 Kennett Square, PA 19348 10 CFR 50.90 July 22, 2003 5928-03-20158 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Three Mile Island, Unit 1 Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
License Amendment Request No. 318 Integrated Leak Rate Test Deferral Submittal of Camera Ready Page
References:
- 1. Letter from M. P. Gallagher (AmerGen Energy Company, LLC) to U. S.
Nuclear Regulatory Commission, dated September 30, 2002
- 2. Letter from T. G. Colburn (U. S. Nuclear Regulatory Commission) to J. L. Skolds (AmerGen Energy Company, LLC), dated February 28, 2003
- 3. Letter from M. P. Gallagher (AmerGen Energy Company, LLC) to U. S.
Nuclear Regulatory Commission, dated March 19, 2003 In the Reference 1 letter, AmerGen Energy Company (AmerGen), LLC, submitted information concerning License Amendment Request No. 318, in accordance with 10 CFR 50.90, requesting an amendment to the Technical Specifications of Operating License No. DPR-50, for Three Mile Island, Unit 1. This proposed change will revise Technical Specifications (TS) Section 6.8.5 ("Reactor Building Leakage Rate Testing Program") to reflect a one-time deferral of the scheduled performance of the next Type A Containment Integrated Leak Rate Test (ILRT) from October 2003 to no later than September 2008. Attached is an updated camera ready page associated with this change.
fvD
LAR No. 318 Integrated Leak Rate Test Deferral July 22, 2003 Page 2 If you have any questions or require additional information, please contact John Hufnagel at (610) 765-5507.
I declare under penalty of perjury that the foregoing is true and correct.
Respectfully, o7 -.?2-03 Executed on Michael P. Gallagher Director, Licensing and Regulatory Affairs AmerGen Energy Company, LLC
Attachment:
Page 6-11 c cc:
H. J. Miller, Administrator, Region I, USNRC C. W. Smith, USNRC, Senior Resident Inspector, TMI-1 D. M. Skay, USNRC, Senior Project Manager File No. 02079
6.8.5 Reactor Building Leakage Rate Testinq Program The Reactor Building Leakage Rate Testing Program shall be established, implemented, and maintained as follows:
A program shall be established to implement the leakage rate testing of the Reactor Building as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, as modified by the following exception to NEI 94-01, Rev. 0, "Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J":
- a.
Section 9.2.3: The first Type A test performed after the September 1993 Type A test shall be performed no later than September 2008.
The peak calculated Reactor Building internal pressure for the design basis loss of coolant accident, Pac, is 50.6 psig.
The maximum allowable Reactor Building leakage rate, La, shall be 0.1 weight percent of containment atmosphere per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Pac.
Reactor Building leakage rate acceptance criteria is s 1.0 La. During the first plant startup following each test performed in accordance with this program, the leakage rate acceptance criteria are s 0.60 La for the Type B and Type C tests and s 0.75 La for the Type A tests.
6-11c Amendment No. 201,