ML092530664
| ML092530664 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 09/14/2009 |
| From: | Gratton C Plant Licensing Branch III |
| To: | Pardee C Exelon Generation Co, Exelon Nuclear |
| Gratton C, NRR/DORL 415-1055 | |
| References | |
| TAC ME1053, TAC ME1054, TAC ME1055, TAC ME1056 | |
| Download: ML092530664 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 14, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME1053 THRU ME1056)
Dear Mr. Pardee By letter to the Nuclear Regulatory Commission (NRC) dated April 7, 2009 (Agencywide Documents Access and Management System Accession Number ML090970914), Exelon Generation Company, LLC, submitted a request to revise the operating license for the subject plants to remove information that is no longer applicable to the units, or to correct titling errors for certain documents referenced in the license.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on September 10, 2009, it was agreed that you would provide a response by October 5,2009.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1055.
Sincerely,
~~L~
Christopher Gratton, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237, 50-249, 50-254, and 50-265
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE LICENSE AMENDMENT REQUEST REGARDING REACTOR COOLANT SYSTEM (RCS) LEAKAGE DETECTION INSTRUMENTATION AND CORE OPERATING LIMITS REPORT (COLR) FOR DRESDEN NUCLEAR POWER STATION (DNPS), UNITS 2 AND 3, AND QUAD CITIES NUCLEAR POWER STATION (QCNPS), UNITS 1 AND 2 DOCKET NOS. 50-237, 50-249; 50-254, AND 50-265 In reviewing the Exelon Generation Company's (EGC's) submittal dated April 7, 2009, related to a request to revise the operating license for the subject plants to remove information that is no longer applicable to the units, or to correct titling errors for certain documents referenced in the license for the subject plants, the Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review:
- 1. With respect to proposed change to Technical Specification (TS) 5.6.5.b, "Core Operating Limits Report [COLR]," the list of approved methodologies consists of General Electric, Combustion Engineering, and Westinghouse topical reports for DNPS Units 2 and 3, and QCNPS Units 1 and 2.
Please provide the following information:
(1) Clarify the need for different vendors' methodologies; (2) Describe the current fuel loading pattern; (3) Justify why other fuel vendor's methodologies are still listed in the COLR TS if there is no mixed core loading pattern; (4) Identify which cycle-specific parameters listed in TS 5.6.5.a is supported by methodologies listed in TS 5.6.5.b; (5) Provide approved date and version for the methodologies listed in TS 5.6.5.b; (6) Provide NRC approved letter or safety evaluation report for proposed TS 5.6.5.b.1 for DNPS and TS 6.6.5.b.2 for QCNPS, Commonwealth Edison Company Topical Report NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods."
- 2. With respect to the request of deletion of license condition from DNPS and QCNPS Facility Operating Licenses, please provide information as follows:
(1) Describe the relationship between generic environmental assessments and an extended maximum rod average burnup limit of 62 gigawatt-days per metric ton of uranium; (2) Clarify any relevant relationship and impact between the license condition and content given in the references (2) and (3) of References Section 7.0 of the submittal; and (3) Provide the proposed maximum burnup limit for the current reactor operation.
ENCLOSURE
-2
- 3. With respect to proposed deletion of footnote from DNPS TS 3.4.5, "RCS Leakage Detection Instrumentation," please describe work done by EGC to repair the failed DNPS Unit 3 component.
ML092530664 NRR-088 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME CGratton THarris SCampbell DATE 9/14/09 9/11/09 9/14/09