ML042570212
| ML042570212 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-033) |
| Issue date: | 09/13/2004 |
| From: | Jabbour K NRC/NRR/DLPM/LPD2 |
| To: | Singer K Tennessee Valley Authority |
| Jabbour K, NRR/DLPM, 415-1496 | |
| References | |
| TAC MC2305 | |
| Download: ML042570212 (4) | |
Text
September 13, 2004 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
SUBJECT:
BROWNS FERRY NUCLEAR PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE ALLOWABLE VALUE FOR REACTOR VESSEL WATER LEVEL (TAC NO. MC2305)
Dear Mr. Singer:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 9, 2004, the Tennessee Valley Authority submitted an application to revise the Technical Specifications and the licensing basis for the Browns Ferry Nuclear Plant, Unit 1. The proposed revision is related to the reduction of the allowable value used for the reactor vessel water level for several instrument functions.
The NRC staff has reviewed your submittal and finds that a response to the enclosed request for additional information is needed before we can complete the review. This request was discussed with Mr. Steven Kane of your staff on August 9, 2004, and it was agreed that a response would be provided within 30 days of receipt of this letter. If you have any questions, please contact me at (301) 415-1496.
Sincerely,
/RA/
Kahtan N. Jabbour, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-259
Enclosure:
Request for Additional Information cc w/encl: See next page
ML042570212 NRR-088 OFFICE PDII-2/PM PDII-2/LA SRSB/SC EEIB/SC PDII-2/SC(A)
NAME KJabbour BClayton FAkstulewicz EMarinos MMarshall DATE 9/10/04 9/10/04 9/10/04 9/13/04 9/13/04
Mr. Karl W. Singer BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. James E. Maddox, Vice President Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Kurt Krueger, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Michael D. Skaggs Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 General Counsel Tennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902 Mr. John C. Fornicola, Manager Nuclear Assurance and Licensing Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Jon R. Rupert, Vice President Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Robert G. Jones Browns Ferry Unit 1 Plant Restart Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Mark J. Burzynski, Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Timothy E. Abney, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611
Enclosure REQUEST FOR ADDITIONAL INFORMATION ALLOWABLE VALUE FOR REACTOR VESSEL WATER LEVEL TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-259 1.
Please provide a copy of the document that calculates the new instrument allowable value for Reactor Vessel Water Level - Low (Level 3) function. Discuss the instrument setpoint methodology used to calculate the allowable values.
2.
The proposed new allowable value of the Reactor Vessel Water Level - Low is about 10 inches below the original allowable value, that will delay the protective action to mitigate the consequence of an accident. Please discuss any impact to the automatic load sequencer initiation which will provide emergency power to the Emergency Core Cooling System (ECCS) related components.
3.
The original Level 3 allowable value in the Reactor Protection System (RPS) was 538 inches, and in the ECCS was 544 inches. The proposed new Level 3 allowable value in the RPS and in the ECCS are set at the same allowable value of 528 inches.
Discuss any impact on system interaction by setting at the same value.
4.
Please provide a simplified figure that shows, as a minimum, the elevations of the water in the reactor vessel for Level 3 and the top of active fuel.
5.
Please discuss the assumptions that resulted in a small reduction of the peak clad temperature for a small-break loss-of-coolant accident analysis.