RBG-46222, Supplement to Amendment Request, Deletion of Technical Specification 3.6.4.4, Shield Building Annulus Mixing System; and Revision of Main Steam Isolation Valve (MSIV) Surveillance Requirement SR 3.6.1.3-10
| ML040500292 | |
| Person / Time | |
|---|---|
| Site: | River Bend  (NPF-047) |
| Issue date: | 02/10/2004 |
| From: | King R Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RBG-46222 | |
| Download: ML040500292 (5) | |
Text
-F Entergy Entergy Operations, Inc.
River Bend Station 5485 U. S. Highway 61N St. Francisville. LA 70775 Fax 225 635 5068 RBG-46222 February 10, 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Supplement to Amendment Request, Deletion of Technical Specification 3.6.4.4 Shield Building Annulus Mixing System; and revision of Main Steam Isolation Valve (MSIV) Surveillance Requirement SR 3.6.1.3.10.
River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47
REFERENCES:
- 1.
Letter from Entergy Operations, Inc (EOI) to US NRC: License Amendment Request Deletion of Technical Specification 3.6.4.4 Shield Building Annulus Mixing System; and revision of Main Steam Isolation Valve (MSIV) Surveillance Requirement SR 3.6.1.3.10, dated October 21, 2003.
Dear Sir or Madam:
By letter (Reference 1), Entergy Operations, Inc. (Entergy) proposed a change to the River Bend Station, Unit 1 (RBS) Technical Specifications (TSs) for License Amendment Request Deletion of Technical Specification 3.6.4.4 Shield Building Annulus Mixing System; and revision of Main Steam Isolation Valve (MSIV) Surveillance Requirement SR 3.6.1.3.10.
On December 3, 2003, Entergy and members of your staff held a call to discuss this submittal. As a result of the call, two questions were determined to need formal response.
Entergy's response is contained in Attachment 1.
There are no technical changes proposed. The original no significant hazards consideration included in Reference 1 is not affected by any information contained in the supplemental letter. There are no new commitments contained in this letter.
If you have any questions or require additional information, please contact Greg Norris at 225-336-6391.
RBG-46222 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on February 10, 2004.
Sincerely, Rick J. King Director Nuclear Safety Assurance RJK/GPN
Attachment:
- 1. Response to Request For Additional Information
Enclosure:
- 1. Information copy of revised River Bend Alternate Source Term LOCA Off-Site and Control Room Dose Analysis Calculation cc:
Mr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 U.S. Nuclear Regulatory Commission Attn: Mr. Michael K. Webb MS 0-7D1 Washington, DC 20555-0001 Louisiana Department of Environmental Quality Office of Environmental Compliance Attn: Mr. Prosanta Chowdhury Surveillance Division P.O. Box 4312 Baton Rouge, LA 70821-4312
RBG-46222 Bcc:
File No.: G9.5, G9.42 File: RBFI-04-0019 File: LAR 2003-21 To RBG-46222 Response to Request for Additional Information to RBG-46222 Page 1 of 1 Response to Request for Additional Information Related to License Amendment Request for Deletion of Technical Specification 3.6.4.4 Shield Building Annulus Mixing System; and revision of Main Steam Isolation Valve (MSIV) Surveillance Requirement SR 3.6.1.3.10.
- 1. During the conference call on December 3, 2003, the NRC reviewer asked that Entergy provide additional detail regarding the testing that was performed to establish that removal of the Annulus Mixing System had no impact on the Standby Gas Treatment System (SGTS) drawdown capability.
In the original submittal, EOI stated that "...a test was performed during RF 1, in the Spring of 2003, to demonstrate that the Standby Gas Treatment System could meet the drawdown requirements without the support of the Shield Building Annulus Mixing System. This was performed by conducting the drawdown test with the Annulus Mixing fans locked out. Test results indicated that the SGTS can meet all of its acceptance criteria under these conditions."
As indicated, that test was performed during RF-1 1 to demonstrate that the Standby Gas Treatment System (SGTS) could meet the existing Technical Specification drawdown requirements (34.5 seconds for the Auxiliary Building and 18.5 seconds for the Annulus) without the support of the Shield Building Annulus Mixing System.
The test was performed using a temporary procedure modeled after the SGTS drawdown surveillance, and provided for locking out the Annulus Mixing System fans during the test evolution. The test results indicated that SGTS would meet the drawdown acceptance criteria independent of the Annulus Mixing System. This test was performed for information only.
The configuration of the Annulus Mixing system, as the name implies, provides for mixing of the annulus atmosphere only. During normal operations of the plant, the Annulus Pressure Control System maintains the Annulus Shield Building at a negative pressure. In response to an initiation signal, the Annulus Pressure Control System isolates, and SGTS is actuated along with the existing Annulus Mixing System. During an event, the Annulus is maintained negative by the Standby Gas Treatment System (SGTS). The testing demonstrated that the SGTS system would perform the drawdown and maintain the annulus as designed without the Annulus Mixing system in service.
- 2. During the conference call, the NRC reviewer also requested that Entergy provide either: 1) all of the inputs and assumptions for the revised dose calculations that support the amendment request, or 2) the whole analysis. The submittal discussed only the specific revisions to the dose analysis. Due to wording in the original submittal, the reviewer indicated that it was not clear that all changes were addressed.
Therefore, Entergy has included, as Enclosure 1, for information only, a copy of the revised Alternate Source Term LOCA Off-Site and Control Room Dose Analysis. This document provides all of the associated assumptions and methodology for this License Amendment Request.