ML070230359
| ML070230359 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/25/2007 |
| From: | Williams J NRC/NRR/ADRO/DORL/LPLIII-2 |
| To: | Crane C Exelon Generation Co |
| Williams J, NRR/DLPM/LPD1, 415-1470 | |
| References | |
| GL-03-001, TAC MB9845, TAC MB9846 | |
| Download: ML070230359 (4) | |
Text
January 25, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2003-01,
?CONTROL ROOM HABITABILITY (TAC NOS. MB9845 AND MB9846)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated December 9, 2003, Exelon Generation Company, LLC submitted a letter responding to Generic Letter 2003-01, ?Control Room Habitability, for the Quad Cities Nuclear Power Station, Units 1 and 2. The NRC staff is reviewing this response, 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 January 8, 2007, it was agreed that you would provide a response by March 9, 2007.
If you have questions regarding this topic, or if circumstances result in the need to revise the requested response date, please contact me at (301) 415-1470.
Sincerely,
/RA/
Joseph F. Williams, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page
Mr. Christopher M. Crane January 25, 2007 President and Chief Nuclear Officer Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2003-01,
?CONTROL ROOM HABITABILITY (TAC NOS. MB9845 AND MB9846)
Dear Mr. Crane:
By letter to the Nuclear Regulatory Commission (NRC) dated December 9, 2003, Exelon Generation Company, LLC submitted a letter responding to Generic Letter 2003-01, ?Control Room Habitability, for the Quad Cities Nuclear Power Station, Units 1 and 2. The NRC staff is reviewing this response, 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 January 8, 2007, it was agreed that you would provide a response by March 9, 2007.
If you have questions regarding this topic, or if circumstances result in the need to revise the requested response date, please contact me at (301) 415-1470.
Sincerely,
/RA/
Joseph F. Williams, Senior Project Manager Plant Licensing Branch III-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-254 and 50-265
Enclosure:
Request for Additional Information cc w/encl: See next page Distribution:
PUBLIC RidsAcrsAcnwMailCenter LPL3-2 R/F RidsRgn3MailCenter RidsNrrDorlLpl3-2 RidsNrrDorlDpr RidsNrrLAEWhitt RidsNrrDprPgcb RidsNrrPMJWilliams RidsNrrDssScvb RidsOgcRp Accession Number: ML070230359 NRR-088 OFFICE PM:LPL3-2 LA:LPL3-2 BC:LPL3-2 NAME JWilliams:mw EWhitt MMarshall DATE 1/25/2007 1/24/2007 1/25/2007 OFFICIAL RECORD COPY
Quad Cities Nuclear Power Station Units 1 and 2 cc:
Site Vice President - Quad Cities Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Plant Manager - Quad Cities Nuclear Power Station Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Manager Regulatory Assurance - Quad Cities Exelon Generation Company, LLC 22710 206th Avenue N.
Cordova, IL 61242-9740 Quad Cities Resident Inspectors Office U.S. Nuclear Regulatory Commission 22712 206th Avenue N.
Cordova, IL 61242 David C. Tubbs MidAmerican Energy Company One River Center Place 106 E. Second, P.O. Box 4350 Davenport, IA 52808-4350 Vice President - Law and Regulatory Affairs MidAmerican Energy Company One River Center Place 106 E. Second Street P.O. Box 4350 Davenport, IA 52808 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock Island, IL 61201 Regional Administrator U.S. NRC, Region III 801 Warrenville Road Lisle, IL 60532-4351 Illinois Emergency Management Agency Division of Disaster Assistance &
Preparedness 110 East Adams Street Springfield, IL 62701-1109 Document Control Desk - Licensing Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President - Operations Support Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Director - Licensing and Regulatory Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Regulatory and Legal Affairs Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Assistant General Counsel Exelon Generation Company, LLC 200 Exelon Way Kennett Square, PA 19348 Manager Licensing - Quad Cities Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President - Midwest Operations Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
Enclosure REQUEST FOR ADDITIONAL INFORMATION QUAD CITIES NUCLEAR POWER STATION, UNITS 1 AND 2 DOCKET NOS. 50-254 AND 50-265 Generic Letter (GL) 2003-01 requested confirmation that your facilitys control room meets the applicable habitability regulatory requirements and that the control room habitability systems are designed, constructed, configured, operated, and maintained in accordance with the facilitys design and licensing bases. GL 2003-01, Item 1a, requested that you confirm that the most limiting unfiltered inleakage into your control room envelope is no more than the value assumed in your design basis radiological analyses for control room habitability.
In your December 9, 2003 (Agencywide Document Access and Management System Accession No. ML033560302), response, you stated that in the event of a loss-of-coolant accident (LOCA), Train ?B is operated and its supply of outside air is filtered by the air filtration unit.
You further stated that during a LOCA, Train ?B the heating, ventilation, and air conditioning (HVAC) system will operate. A review of your updated final safety analysis report (UFSAR)
(Rev. 6, 10/2001) stated that in the event of a LOCA, Train ?A or Train ?B is operated and its supply of outdoor air is filtered by an air filtration unit.
In your December 9, 2003, response, you also stated that the tested unfiltered inleakage for Train ?A is 297 cubic feet per minute (cfm) (222 +/- 75), which is more than the unfiltered inleakage of 260 cfm assumed in your LOCA radiological analysis. You further stated that the tested inleakage for Train ?B was 88 CFM (88 +/-74) which was less than that value. Since your response to GL 2003-01 was submitted, an amendment was issued for Quad Cities Nuclear Power Station, Units 1 and 2 (Quad Cities) to adopt alternate source term methodology which increases the assumed unfiltered inleakage from 260 cfm to 400 cfm which now bounds the previous tracer gas test results for both Train ?A and Train ?B.
In your December 9, 2003 response, you infer that Train ?B is redundant to Train ?A by stating that ?...Quad Cities committed to install a redundant control room HVAC system (Train ?B).
You further state that Train ?A is non-safety related and that Train ?B is safety related.
Based on the above, we are requesting that you provide the following additional information:
- 1. The reason why your response to GL 2003-01 differed from the information contained in your UFSAR. Since your UFSAR states that Train ?A or Train ?B can be operated during a LOCA, explain why in your response to Quad Cities GL 2003-01, you only indicated that Train
?B would operate during a LOCA.
- 2. An explanation of how you concluded that ?the most limiting measured unfiltered inleakage is bounded by the value assumed in the design basis radiological analyses for control room habitability when the tracer gas test results for Train ?A were higher than that assumed value and your UFSAR states that Train A or Train B can be operated during a LOCA.