CNRO-2006-00048, Request for Alternative ANO1-PT-001, Response to Request for Additional Information
| ML062970429 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/16/2006 |
| From: | Burford F Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNRO-2006-00048 | |
| Download: ML062970429 (5) | |
Text
~Entergy Entergy Operations, Inc.
1340 Echelon Parkway Jackson, Mississippi 39213-8298 Tel 601-368-5758 F. G. Burford Acting Director Nuclear Safety & Licensing CNRO-2006-00048 October 16, 2006 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Request for Alternative ANO1-PT-001 Response to a Request for Additional Information Arkansas Nuclear One, Unit 1 Docket No. 50-313 License No. DPR-51
REFERENCE:
Entergy letter CNRO-2006-00022 to the NRC dated April 24, 2006
Dear Sir or Madam:
In the referenced letter, Entergy Operations, Inc. (Entergy) submitted to the NRC staff Request for Alternative ANO1-PT-001, which requests approval to visually examine the extended reactor coolant pressure boundary (RCPB) piping between the first and second normally closed isolation valves during the Class 2 system leakage test conducted each inspection interval as an alternative to ASME Section Xl IWB-5222(b). In a recent telephone conversation regarding the request, the NRC requested that additional information be provided; specifically, the dimensions for the piping associated with Decay Heat Removal Loops "A" and "B".
In response to this request for additional information, Entergy has enclosed revised Figures 1 and 2 from ANO1-PT-001 that provide the requested information. These figures replace those previously contained in the referenced letter.
Should you have any questions regarding this submittal, please contact Guy Davant at (601) 368-5756.
This letter contains no commitments.
Very truly yours, FGB/GHD/ghd
Enclosure:
Revised Figures 1 and 2 for Request for Alternative ANO1-PT-001 Aw47
CNRO-2006-00048 Page 2 of 2 cc:
Mr. W. A. Eaton (ECH)
Mr. J. S. Forbes (ANO)
Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 U. S. Nuclear Regulatory Commission Attn: Mr. Drew Holland MS O-7D1 Washington, DC 20555-0001 NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847
ENCLOSURE CNRO-2006-00022 REVISED FIGURES 1 AND 2 FOR REQUEST FOR ALTERNATIVE ANO1-PT-001
Low Pressure Injection Pump A I
PIPING DIAMETERS & LENGTHS A = 8" dia., 7' 1" length B = 1" dia., 12" length C = 12" dia., 11" length D = 12" dia., 11" length expanding to 14" dia., 7.5" length E = 14" dia., 11 length F = 1" dia., 12" length G = 14" dia., 11" length 7DH-18]
DH-13B Low Pressure Injection Pump B p A High Pressure Injection Pumps NOTE: Test boundary shown in bold.
FIGURE 1 DECAY HEAT REMOVAL SYSTEM LOOP "A"
Low Pressure Injection Pump A Low Pressure Injection Pump B PIPING DIAMETERS & LENGTHS PIPING DIAMETERS & LENGTHS A = 8" dia., 9' 3.5" length B = 12" dia., 7.5" length expanding to 14" dia., 11" length C = 14" dia., 1' 9" length D = 14" dia., 11" length E = 14" dia., 9'6.5" length F = 1" dia., 12" length NOTE: Test boundary shown in bold.
High Pressure Injection Pumps FIGURE 2 DECAY HEAT REMOVAL SYSTEM LOOP "B"