ML092670536
| ML092670536 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 09/29/2009 |
| From: | David M Plant Licensing Branch III |
| To: | Pardee C Exelon Nuclear |
| david marshall NRR/DORL 415-1547 | |
| References | |
| GL-08-001, TAC MD7797, TAC MD7798, TAC MD7804, TAC MD7805 | |
| Download: ML092670536 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 29, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNITS 1 AND 2, AND BYRON STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2008-01, "MANAGING GAS ACCUMULATION IN EMERGENCY CORE COOLING, DECAY HEAT REMOVAL, AND CONTAINMENT SPRAY SYSTEMS" (TAC NOS. MD7797, MD7798, MD7804, AND MD7805)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated October 14, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082880706), as supplemented by letters dated January 20 and July 7,2009 (ADAMS Accession Nos.
ML090210304 and ML091880507, respectively) Exelon Generation Company, LLC (the licensee) provided a response to the subject generic letter for Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2.
The NRC staff is reviewing your letters and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosed Request for Additional Information (RAI). Your staff has agreed to provide a response to this RAI within 60 days from the date of this letter.
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) 415-1547.
Sin.ce.relY,....
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Mar/hall J. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BRAIDWOOD STATION, UNITS 1 AND 2 AND BYRON STATION, UNIT NOS. 1 AND 2 DOCKET NOS. STN 50-456, STN 50-457 STN 50-454, AND STN 50-455 By letter to the Nuclear Regulatory Commission (NRC) dated October 14, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML082880706), as supplemented by letters dated January 20 and July 7,2009 (ADAMS Accession Nos.
ML090210304 and ML091880507, respectively) Exelon Generation Company, LLC (the licensee) provided a response to NRC Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," for Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2. The NRC staff is reviewing the letters and requires additional information to determine whether the licensee has acceptably demonstrated "that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance" as stated in the PURPOSE section of the GL.
Guidance on NRC staff expectations is provided by Reference 1, which is generally consistent with Nuclear Energy Institute (NEI) guidance provided to industry in Reference 2 as clarified in later NEI communications. The NRC staff recommends that the licensee consult Reference 1 when responding to the following:
- 1.
Describe the revisions to be made to the emergency core cooling, decay heat removal, chemical and volume control, and containment spray systems' fill and vent procedures, particularly with respect to instrument lines.
- 2.
The aforementioned revisions were to be completed by December 31,2008. What is the status of the revisions?
- 3.
Describe the revisions to be made to the emergency core cooling, decay heat removal, chemical and volume control, and containment spray systems' periodic venting procedures, particularly with respect to acceptance criteria and ultrasonic testing.
- 4.
The aforementioned revisions were to be completed by April 30, 2009. What is the status of the revisions?
- 5.
If periodic venting of the emergency core cooling, decay heat removal, and chemical and volume control systems is performed without reference to specific gas volume acceptance criteria that must be met to satisfy the surveillances, then how is it determined that the surveillance intervals are adequate (Le., intervals are short enough to detect the formation of voids before they become large enough to pose a threat to safety-related equipment)?
Enclosure
- 2
- 6.
Training was not identified in the GL, but is considered by the NRC staff to be a necessary part of applying procedures and other activities when addressing the issues identified in the GL. This was identified in the Reference 2 NEI template as an item that should be addressed in the GL. This is not addressed in your response. Please provide a brief description of planned training and its schedule.
REFERENCES:
- 1.
Ruland, William H., "Preliminary Assessment of Responses to Generic Letter 2008-01,
'Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems,' and Future NRC Staff Review Plans," NRC letter to James H. Riley, Nuclear Energy Institute, ML091390637, May 28,2009.
- 2.
Riley, James H., "Generic Letter (GL) 2008-01, 'Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Contain Spray Systems' Evaluation and 3 Month Response Template," Letter to Administrative Points of Contact from Director, Engineering, Nuclear Generation Division, Nuclear Energy Institute,, "Generic Letter 2008-01 Response Guidance," March 20, 2008.
ML090210304 and ML091880507, respectively) Exelon Generation Company, LLC (the licensee) provided a response to the subject generic letter for Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2.
The NRC staff is reviewing your letters and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosed Request for Additional Information (RAI). Your staff has agreed to provide a response to this RAI within 60 days from the date of this letter.
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) 415-1547.
Sincerely, IRA!
Marshall J. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN-456, STN-457, STN 50-454, and STN 50-455
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrPMByron Resource RidsNrrDssSrxb Resource LPL3-2 RtF RidsNrrPMBraidwood Resource RidsOgcRp Resource RidsNrrDorlLpl3-2 Resource RidsAcrsAcnw_MailCTR Resource SMiranda, NRR RidsNrrLATHarris Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No*.. ML092670536
- RAI Memo Date NRR-088 OFFICE LPL3-2/PM LPL3-2/LA DSS/SRXB/BC LPL3-2/BC NAME MDavid THarris GCranston*
SCampbell DATE 9/28/09 9/25/09 09/09/09 9129109