ML042660013
| ML042660013 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 09/30/2004 |
| From: | Milano P NRC/NRR/DLPM/LPD1 |
| To: | Kansler M Entergy Operations |
| Milano P, NRR/DLPM , 415-1457 | |
| References | |
| TAC MC3351 | |
| Download: ML042660013 (5) | |
Text
September 30, 2004 Mr. Michael R. Kansler, President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - REQUEST FOR ADDITIONAL INFORMATION REGARDING AMENDMENT APPLICATION FOR ALTERNATE SOURCE TERM (TAC NO. MC3351)
Dear Mr. Kansler:
On June 2, 2004, Entergy Nuclear Operations, Inc. (Entergy) submitted an application for a proposed amendment to the Technical Specifications (TSs) for Indian Point Nuclear Generating Unit No. 3 to fully adopt the alternate source term (AST) methodology for design-basis accident dose consequence evaluations in accordance with 10 CFR 50.67. Specifically, the amendment would revise the TS definition regarding dose equivalent iodine and TS Section 5.5.10, Ventilation Filter Testing Program. The AST methodology for the fuel-handling accident was previously approved in Amendment No. 215, dated March 17, 2003.
The Nuclear Regulatory Commission staff is reviewing the information provided in the June 2 application and has determined that additional information is needed to complete its review.
The specific questions regarding containment sump pH and iodine removal coefficients are found in the enclosed request for additional information (RAI). The staff will provide possible questions regarding other areas of its review in a separate letter. During a telephone call on September 21, 2004, the Entergy staff indicated that a response to the RAI would be provided within 45 days.
Please contact me at (301) 415-1457 if you have any questions on this issue.
Sincerely,
/RA/
Patrick D. Milano, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-286 cc: See next page
ML042660013 OFFICE PDI-1/PM PDI-1/LA EMCB/SC PDI-1/SC NAME PMilano SLittle LLund RLaufer DATE 9/23/04 9/30/04 9/23/04 9/28/04
Indian Point Nuclear Generating Unit No. 3 cc:
Mr. Gary J. Taylor Chief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Fred Dacimo Site Vice President Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Christopher Schwarz General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 2 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Danny L. Pace Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Brian OGrady Vice President Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John McCann Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Michael J. Colomb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. James Comiotes Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Mr. Patric Conroy Manager, Licensing Entergy Nuclear Operations, Inc.
Indian Point Energy Center 295 Broadway, Suite 1 P. O. Box 249 Buchanan, NY 10511-0249 Mr. John M. Fulton Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspectors Office Indian Point 3 U. S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511-0337
Indian Point Nuclear Generating Unit No. 3 cc:
Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy Electric Division New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Ray Albanese Executive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592 Ms. Stacey Lousteau Treasury Department Entergy Services, Inc.
639 Loyola Avenue Mail Stop: L-ENT-15E New Orleans, LA 70113 Mr. William DiProfio PWR SRC ConsultaNT 139 Depot Road East Kingston, NH 03827 Mr. Dan C. Poole PWR SRC Consultant 20 Captains Cove Road Inglis, FL 34449 Mr. William T. Russell PWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232 Mr. Alex Matthiessen Executive Director Riverkeeper, Inc.
25 Wing & Wing Garrison, NY 10524 Mr. Paul Leventhal The Nuclear Control Institute 1000 Connecticut Avenue NW Suite 410 Washington, DC, 20036 Mr. Karl Coplan Pace Environmental Litigation Clinic 78 No. Broadway White Plains, NY 10603 Mr. Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Robert D. Snook Assistant Attorney General State of Connecticut 55 Elm Street P.O. Box 120 Hartford, CT 06141-0120 Mr. David Lochbaum Nuclear Safety Engineer Union of Concerned Scientists 1707 H Street NW, Suite 600 Washington, DC 20006
Enclosure REQUEST FOR ADDITIONAL INFORMATION REGARDING FULL-SCOPE ADOPTION OF ALTERNATE SOURCE TERM ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286 In a letter dated June 2, 2004 (ADAMS Accession No. ML041600619), Entergy Nuclear Operations (Entergy or the licensee) submitted an application for a proposed amendment to the Technical Specifications (TSs) for Indian Point Nuclear Generating Unit No. 3 to fully adopt the alternate source term (AST) methodology for design-basis accident dose consequence evaluations in accordance with 10 CFR 50.67. The Nuclear Regulatory Commission (NRC) staff has the following questions regarding the information provided:
- 1.
In order to complete its evaluation, the staff needs to review the general assumptions and calculations used by the licensee to prove that the containment sump pH will be maintained above seven throughout the duration of the accident.
Describe the procedure utilized for calculating the pH of the containment sump water during the 30-day period after a loss-of-coolant accident. If the calculations were performed manually, describe the methodology and provide sample calculations. If a computer code was used, provide the input to the code and the results calculated by it.
- 2.
NUREG-0800, Standard Review Plan Section 6.5.2, Containment Spray as a Fission Product Cleanup System, states that the coefficient representing the removal of elemental iodine by wall deposition is calculated and is used as input in a computer model used for dose calculations.
Provide the value calculated for the removal coefficient of elemental iodine by wall deposition. If this value was not needed in the calculations, provide the technical basis for not using it.
- 3.
NUREG-0800 states that the maximum decontamination factor (DF) is 200 for elemental iodine. If the DF results in a number less than 200, then it is expected that this new number will be used in the calculations as it is more conservative. In the Containment Spray Iodine Removal Model section of the IP3 Updated Final Safety Analysis Report (UFSAR), the licensee calculated the DF to be approximately 160. This number is reduced to 100 to account for the instantaneous plateout and this was the number used in your UFSAR analysis. On page 9 of the June 2 submittal, the licensee stated that it used 200 as the value for the DF.
Clarify the apparent discrepancy between the information in the June 2 submittal and the UFSAR. Discuss whether another DF was calculated for the AST amendment and provide its value.