ML032260325
| ML032260325 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/11/2003 |
| From: | St.Pierre G Florida Power & Light Energy Seabrook |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-03-001, NYN-03070 | |
| Download: ML032260325 (2) | |
Text
FPL Energy FPL Energy Seabrook Station Seabrook Station P.O. Box 300 Seabrook, NH 03874 (603) 773-7000 August 11, 2003 Docket No. 50-443 NYN - 03070 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station 60-Day Response to Generic Letter 2003-01 Control Room Habitability This letter provides the FPL Energy Seabrook, LLC (FPLE Seabrook) 60-day response to Generic Letter (GL) 2003-01, "Control Room Habitability", for Seabrook Station. Recent industry experience has demonstrated that measured in-leakage testing using the American Society of Testing and Materials (ASTM) Standard E471 methodology typically results in greater in-leakage than that assumed in the current license bases.
Seabrook Station is conservatively assuming that tracer gas testing, planned for August 2003, will demonstrate that current design basis in-leakage assumptions may not be met. Thus, Seabrook Station may be unable to provide the information requested in item I of GL 2003-01 by the required December 9,2003 180-day GL response date. In addition, Seabrook Station plans to submit a proposed license amendment to the NRC to adopt the 10 CFR 50.67 alternate source term (AST) methodology for assessing the radiological consequences of design basis events. The approval and implementation of the planned license amendment application is not expected to meet the required GL 2003-01 response date.
Seabrook Station is currently evaluating potential control room envelope (CRE) deficiencies.
CRE leak testing is scheduled for August 2003 using the methods of ASTM E74 1, "Standard Test Method for Determining Air Change in a Single Zone by Means of a Tracer Gas Dilution."
Test results will be evaluated and any deficiencies will be addressed under the FPLE Seabrook corrective action program.
I'D:>
I
USNRC NYN 03070 /Page 2 Implementation of the revised accident source term at Seabrook Station will use methods prescribed in Regulatory Guide 1.183, "Alternate Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors."
10 CFR 50.67, Accident Source Term, requires that a revision of the design bases accident source term be approved by a license amendment under 10 CFR 50.90. The proposed license amendment for Seabrook Station using an alternate radiological source term is scheduled for submittal in the Fourth Quarter of 2003.
Upon approval of the proposed license amendment, FPLE Seabrook will complete its response to item 1 of GL 2003-01. FPLE Seabrook will keep the NRC Project Manager for Seabrook Station advised of schedule progress.
If you have any questions, please contact James M. Peschel, Regulatory Programs Manager, at (603) 773-7194.
Very truly yours, FPL ENERGY SEABROOK, LLC Gene F. St.Pierre Station Director cc:
H. J. Miller, Region I Administrator V. Nerses, NRC Project Manager, Project Directorate 1-2 G. T. Dentel, NRC Senior Resident Inspector