2CAN030804, Response to Request for Additional Information Emergency Core Cooling System Performance Analysis
| ML080810198 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/20/2008 |
| From: | James D Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2CAN030804 | |
| Download: ML080810198 (4) | |
Text
2CAN030804 March 20, 2008 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001
SUBJECT:
Response to Request for Additional Information Emergency Core Cooling System Performance Analysis Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
REFERENCE:
- 1. Entergy Letter to NRC dated July 31, 2007 Emergency Core Cooling System Performance Analysis
Dear Sir or Madam:
By letter dated July 31, 2007 (Reference 1), Entergy Operations, Inc. (Entergy) requested an NRC review of the Arkansas Nuclear One, Unit 2 (ANO-2) revised Emergency Core Cooling System (ECCS) Performance Analysis that supports the implementation of Next Generation Fuel (NGF).
During the review of the Reference 1 submittal, the NRC issued a Request for Additional Information (RAI) that was informally transmitted to Entergy on March 18, 2008. The RAI asks for a statement that Entergy and its Loss of Coolant Accident (LOCA) analyses vendor have ongoing processes that assure ANO-2 LOCA analyses input values bound as-operated ANO-2 plant values for those parameters. The RAI and Entergys response to the RAI is included in. As discussed during the March 18, 2008, conference call with the NRC, this response is consistent with the response provided by Entergys Waterford, Unit 3 nuclear facility to the same request.
This letter contains no commitments.
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Arkansas Nuclear One
2CAN030804 Page 2 of 2 If you have any questions or require additional information, please contact Bob Clark at 479-858-4663.
Sincerely, DEJ/rwc Attachments: 1.
Response to Request for Additional Information Related to the Processes to Assure LOCA Analysis Inputs Bound As-Operated Plant Values cc:
Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U.S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS O-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437
ATTACHMENT 1 2CAN030804 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROCESSES TO ASSURE LOCA ANALYSIS INPUTS BOUND AS-OPERATED PLANT VALUES to 2CAN030804 Page 1 of 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE PROCESSES TO ASSURE LOCA ANALYSIS INPUTS BOUND AS-OPERATED PLANT VALUES NRC Question:
Describe any ongoing processes that assure that the Large Break Loss of Coolant Accident (LBLOCA) and the Small Break Loss of Coolant Accident (SBLOCA) analyses input values for peak cladding temperature-sensitive parameters bound their as-operated plant values.
Response
Consistent with the Waterford Unit 3 response to this same request, ANO-2 and its vendor, Westinghouse Electric Company, LLC, continue to have ongoing processes, which assure that LOCA analysis input values bound the as-operated plant values for those parameters.
Entergy procedure NF-105, Reload Process, Revision 3 (dated January 22, 2004) provides guidance with regard to development of cycle-specific groundrules. Specifically, subsections 4.4.8.4, 5.4.3.3, 5.4.3.4 and 5.4.3.5 of this procedure provide the applicable controls for the groundrules document. The groundrules document is one of the processes used to assure that LOCA analysis input values bound as-operated plant values. The Arkansas Nuclear One, Unit 2 Cycle 20 (number changes each fuel cycle) Groundrules document is developed early in the reload analysis process for each fuel cycle.Section III of this document presents the groundrules that contain safety analysis input parameter values to be used in the reload analyses. This section is to be reviewed for changes and for accuracy by ANO-2, Entergy (PWR Fuels), and the fuel vendor personnel at the start of each reload as a minimum. As stated in that document, the groundrules serve as an interface between ANO-2 and the fuel vendor, Westinghouse, for defining plant equipment parameters which reflect current (or expected) plant characteristics that are to be used in the safety analyses for the subsequent cycle. The information contained in the groundrules is reviewed for changes and for accuracy by Entergy and fuel vendor personnel each cycle. The groundrules information is independently verified to be applicable to ANO-2 and is then available as inputs to the safety analyses. The information provided in the groundrules includes reference sources for the values given. These sources may include, but are not limited to, ANO-2 operating procedures, Technical Specifications, equipment technical manuals, and Entergy calculations, in addition to fuel vendor calculations and analyses. These cross-references are reviewed by both Entergy and the fuel vendor ensure that analysis values, including those associated with the LOCA analyses, bound actual plant design and operating conditions.