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| number = ML14114A563 | | number = ML14114A563 | ||
| issue date = 09/10/2014 | | issue date = 09/10/2014 | ||
| title = | | title = Request for Additional Information Regarding License Amendment Request Related to Reactor Building Vital Area Access Control | ||
| author name = Lamb J | | author name = Lamb J | ||
| author affiliation = NRC/NRR/DORL/LPLI-2 | | author affiliation = NRC/NRR/DORL/LPLI-2 | ||
| addressee name = Pacilio M | | addressee name = Pacilio M | ||
| addressee affiliation = Exelon Nuclear | | addressee affiliation = Exelon Nuclear | ||
| docket = 05000219 | | docket = 05000219 | ||
| license number = | | license number = | ||
| contact person = Lamb J | | contact person = Lamb J, NRR/DORL/LPLI-2 | ||
| case reference number = TAC MF3295 | | case reference number = TAC MF3295 | ||
| document type = Letter, Request for Additional Information (RAI) | | document type = Letter, Request for Additional Information (RAI) | ||
| page count = 6 | | page count = 6 | ||
| project = TAC:MF3295 | |||
| stage = RAI | |||
}} | }} | ||
=Text= | |||
{{#Wiki_filter:OFFICIAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2014 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | |||
==SUBJECT:== | |||
OYSTER CREEK NUCLEAR GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST RELATED TO REACTOR BUILDING VITAL AREA ACCESS CONTROL (TAC NO. MF3295) | |||
==Dear Mr. Pacilio:== | |||
By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90, to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access for certain portions of the reactor building at OCNGS. The attachment to the letter dated December 19, 2013, contained Safeguards Information and has been withheld from public disclosure. | |||
In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives, and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55. | |||
The NRC staff is currently reviewing the submittal and is enclosing a request for additional information (RAI) to support its review. A draft of these questions was previously sent to Mr. | |||
Richard Gropp of your staff on August 12, 2014, with an opportunity to have a teleconference to ensure that Exelon understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed. | |||
Enclosure 2 transmitted herewith contains Security-Related Information. When separated from Enclosure 2, this document is decontrolled. | |||
OFFICIAL USE ONLY SECURITY RELATED INFORMATION | |||
OFFICIAL USE ONLY SECURITY RELATED INFORMATION M. Pacillo A call was held on August 27, 2014, and Mr. Gropp agreed that Exelon would respond to the RAI by November 5, 2014. Please note that if you do not respond to the RAI by November 5, 2014, the NRC staff may reject your license amendment request under the provisions of 10 CFR 2.1 08, "Denial of application for failure to supply information." | |||
If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov. | |||
Sincerely, | |||
. Lamb, Senior Project Manager PI Licensing Branch 1-2 Di | |||
* ion of Operating Reactor Licensing 0 1ce of Nuclear Reactor Regulation Docket No. 50-219 | |||
==Enclosures:== | |||
: 1. Request for Additional Information | |||
: 2. Request for Additional Information (Security-Related Information) cc w/encl 1: Distribution via Listserv OFFICIAL USE ONLY SECURITY RELATED INFORMATION | |||
OFFICIAL US& ONLY SECURITY R&LAT&D INFORMATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING THE REACTOR BUILDING VITAL AREA ACCESS CONTROL OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATION COMPANY. LLC DOCKET NO. 50-219 Security-related information has been redacted from this document. | |||
Redacted information is identified by blank space enclosed within double brackets as shown here (( )). | |||
By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90 to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access at OCNGS. The enclosure to the letter contained Safeguards Information and has been withheld from public disclosure. | |||
In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55. The NRC staff is currently reviewing the submittal and has determined that the additional information requested below is needed to support its review. | |||
REGULA TORY BASIS The regulations in 10 CFR 73.55(e)(9)(i), state that "[v]ital equipment must be located only within vital areas, which must be located within a protected area so that access to vital equipment requires passage through at least two physical barriers, except as otherwise approved by the Commission and identified in the security plans." | |||
The regulations in 10 CFR 73.55(e)(9)(ii) state that "[t]he licensee shall protect all vital area access portals and vital area emergency exits with intrusion detection equipment and locking Enclosure 1 OFFICIAL USE ONLY SECURITY REbATED INFORMATION | |||
OFFICIAl USE! ONlY Si!CURITY Ri!bATE!D INFORMATION devices that allow rapid egress during an emergency and satisfy the vital entry control requirements of this section." | |||
The regulation in 10 CFR 73.55(e)(9)(iii) states that, "[u]noccupied vital areas must be locked and alarmed." | |||
Consistent with 10 CFR 73.55(r)(3), the licensee shall submit a technical basis for each proposed alternative measure. The basis must include an analysis or assessment that demonstrates how the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii). | |||
REQUEST FOR ADDITIONAL INFORMATION The following additional licensing basis information is needed to justify the need to apply 10 CFR 73.55(r) and to justify that the proposed alternative measures meet the performance requirements of 10 CFR 73.55(b). | |||
(( | |||
OFFICIAl USE! ONlY SECURITY REbATED INFORMATION | |||
OFFICIAL US& ONLY SliCURITY RlilATiiD INFORMATION | |||
)) | |||
OFFICIAL US& ONLY SECURITY REbATI5D INFORMATION | |||
ML14114A563 *via email OFFICE NRR/LPL1-2/PM N RR/LPL 1-2/LA NSIR/BC NRR/LPL 1-2/BC(A) NRR/LPL 1-2/PM Jlamb A Baxter* DHuyck* RSchaaf Jlamb NAME w/comment DATE 08/24/14 09/05/14 09/08/14 9/10/14 9/10/14}} |
Latest revision as of 22:22, 19 March 2020
ML14114A563 | |
Person / Time | |
---|---|
Site: | Oyster Creek |
Issue date: | 09/10/2014 |
From: | John Lamb Plant Licensing Branch 1 |
To: | Pacilio M Exelon Nuclear |
Lamb J, NRR/DORL/LPLI-2 | |
References | |
TAC MF3295 | |
Download: ML14114A563 (6) | |
Text
OFFICIAL USE ONLY SECURITY RELATED INFORMATION UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2014 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
OYSTER CREEK NUCLEAR GENERATING STATION- REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST RELATED TO REACTOR BUILDING VITAL AREA ACCESS CONTROL (TAC NO. MF3295)
Dear Mr. Pacilio:
By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90, to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access for certain portions of the reactor building at OCNGS. The attachment to the letter dated December 19, 2013, contained Safeguards Information and has been withheld from public disclosure.
In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives, and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55.
The NRC staff is currently reviewing the submittal and is enclosing a request for additional information (RAI) to support its review. A draft of these questions was previously sent to Mr.
Richard Gropp of your staff on August 12, 2014, with an opportunity to have a teleconference to ensure that Exelon understood the questions and their regulatory basis, as well as to verify that the information was not previously docketed.
Enclosure 2 transmitted herewith contains Security-Related Information. When separated from Enclosure 2, this document is decontrolled.
OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL USE ONLY SECURITY RELATED INFORMATION M. Pacillo A call was held on August 27, 2014, and Mr. Gropp agreed that Exelon would respond to the RAI by November 5, 2014. Please note that if you do not respond to the RAI by November 5, 2014, the NRC staff may reject your license amendment request under the provisions of 10 CFR 2.1 08, "Denial of application for failure to supply information."
If you have any questions regarding this letter, please feel free to contact me at (301) 415-3100 or by e-mail at John.Lamb@nrc.gov.
Sincerely,
. Lamb, Senior Project Manager PI Licensing Branch 1-2 Di
- ion of Operating Reactor Licensing 0 1ce of Nuclear Reactor Regulation Docket No. 50-219
Enclosures:
- 1. Request for Additional Information
- 2. Request for Additional Information (Security-Related Information) cc w/encl 1: Distribution via Listserv OFFICIAL USE ONLY SECURITY RELATED INFORMATION
OFFICIAL US& ONLY SECURITY R&LAT&D INFORMATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST REGARDING THE REACTOR BUILDING VITAL AREA ACCESS CONTROL OYSTER CREEK NUCLEAR GENERATING STATION EXELON GENERATION COMPANY. LLC DOCKET NO. 50-219 Security-related information has been redacted from this document.
Redacted information is identified by blank space enclosed within double brackets as shown here (( )).
By letter dated December 19, 2013 (Agencywide Documents Access and Management System Accession No. ML13358A245), Exelon Generation Company, LLC (Exelon or the licensee) submitted the Oyster Creek Nuclear Generating Station (OCNGS) license amendment request pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR), Section 50.90 to implement an alternative measure to satisfy the regulatory requirements of 10 CFR 73.55(e)(9) relating to controlling vital area access at OCNGS. The enclosure to the letter contained Safeguards Information and has been withheld from public disclosure.
In accordance with the requirements of 10 CFR 73.55(r), the U.S. Nuclear Regulatory Commission (NRC) may authorize an applicant or licensee to provide a measure for protection against radiological sabotage other than one required by 10 CFR 73.55, if the applicant or licensee demonstrates that the measure meets the same performance objectives and requirements as specified in 10 CFR 73.55(b), and the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirement in 10 CFR 73.55. The NRC staff is currently reviewing the submittal and has determined that the additional information requested below is needed to support its review.
REGULA TORY BASIS The regulations in 10 CFR 73.55(e)(9)(i), state that "[v]ital equipment must be located only within vital areas, which must be located within a protected area so that access to vital equipment requires passage through at least two physical barriers, except as otherwise approved by the Commission and identified in the security plans."
The regulations in 10 CFR 73.55(e)(9)(ii) state that "[t]he licensee shall protect all vital area access portals and vital area emergency exits with intrusion detection equipment and locking Enclosure 1 OFFICIAL USE ONLY SECURITY REbATED INFORMATION
OFFICIAl USE! ONlY Si!CURITY Ri!bATE!D INFORMATION devices that allow rapid egress during an emergency and satisfy the vital entry control requirements of this section."
The regulation in 10 CFR 73.55(e)(9)(iii) states that, "[u]noccupied vital areas must be locked and alarmed."
Consistent with 10 CFR 73.55(r)(3), the licensee shall submit a technical basis for each proposed alternative measure. The basis must include an analysis or assessment that demonstrates how the proposed alternative measure provides a level of protection that is at least equal to that which would otherwise be provided by the specific requirements of 10 CFR 73.55(e)(9)(i) through (iii).
REQUEST FOR ADDITIONAL INFORMATION The following additional licensing basis information is needed to justify the need to apply 10 CFR 73.55(r) and to justify that the proposed alternative measures meet the performance requirements of 10 CFR 73.55(b).
((
OFFICIAl USE! ONlY SECURITY REbATED INFORMATION
OFFICIAL US& ONLY SliCURITY RlilATiiD INFORMATION
))
OFFICIAL US& ONLY SECURITY REbATI5D INFORMATION
ML14114A563 *via email OFFICE NRR/LPL1-2/PM N RR/LPL 1-2/LA NSIR/BC NRR/LPL 1-2/BC(A) NRR/LPL 1-2/PM Jlamb A Baxter* DHuyck* RSchaaf Jlamb NAME w/comment DATE 08/24/14 09/05/14 09/08/14 9/10/14 9/10/14