ML053620072

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Request for Additional Information for the Review of the Oyster Creek Nuclear Generating Station, License Renewal Application
ML053620072
Person / Time
Site: Oyster Creek
Issue date: 12/28/2005
From: Ashley D
NRC/NRR/ADRO/DLR/RLRB
To: Swenson C
AmerGen Energy Co
Ashley, D J, NRR/DLR/RLRB, 415-3191
References
%dam200606, -RFPFR, TAC MC7624
Download: ML053620072 (7)


Text

December 28, 2005 C. N. Swenson Site Vice President AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION (TAC NO. MC7624)

Dear Mr. Swenson:

By letter dated July 22, 2005, AmerGen Energy Company, LLC (AmerGen or the applicant) submitted to the U.S. Nuclear Regulatory Commission (NRC or the staff) an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew the operating license for Oyster Creek Nuclear Generating Station. The NRC staff is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.

These questions were discussed with members of your staff during a conference call on December 2, 2005. A mutually agreeable date for a response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-3191 or via e-mail at DJA1@nrc.gov.

Sincerely,

/RA/

Donnie J. Ashley, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-219

Enclosure:

As stated cc w/encls: See next page

ML053620072 OFFICE PM:RLRB LA:DLR BC:RLRB (A)

NAME DJAshley YEdmonds LLund DATE 12/20/05 12/20/05 12/23/05

Oyster Creek Nuclear Generating Station cc:

Chief Operating Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Senior Vice President - Nuclear Services AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Site Vice President - Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Vice President - Mid-Atlantic Operations AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348 Kathryn M. Sutton, Esquire Morgan, Lewis, & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004 Kent Tosch, Chief New Jersey Department of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Vice President - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Vice President - Operations Support AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mayor of Lacey Township 818 West Lacey Road Forked River, NJ 08731 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 445 Forked River, NJ 08731 Director - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Manager Licensing - Oyster Creek Exelon Generation Company, LLC 200 Exelon Way, KSA 3-E Kennett Square, PA 19348 Plant Manager Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Regulatory Assurance Manager Oyster Creek AmerGen Energy Company, LLC P.O. Box 388 Forked River, NJ 08731 Vice President, General Counsel and Secretary AmerGen Energy Company, LLC 2301 Market Street, S23-1 Philadelphia, PA 19101 Ron Bellamy, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415

Oyster Creek Nuclear Generating Station cc:

Correspondence Control Desk AmerGen Energy Company, LLC P.O. Box 160 Kennett Square, PA 19348 License Renewal Manager Exelon Generation Company, LLC 200 Exelon Way, Suite 210 Kennett Square, PA 19348 Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Mr. Christopher M. Crane President and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555

Letter to C. N. Swenson From Donnie J. Ashley dated: December 28, 2005

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION (TAC NO. MC7624)

DISTRIBUTION:

PUBLIC SSmith (srs3)

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Enclosure OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION (LRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

RAI 2.3.3.14-1 License renewal Drawing LR-BR-2005, Sheet 4 shows strainers located at C-7, C-8, F-7 and F-8. These strainers are shown as being within the scope of license renewal and serve a pressure boundary intended function. However, LRA Table 2.3.3.14 does not include the component type strainer as a component type subject to an aging management review (AMR).

Clarify if these strainers are subject to an AMR, or justify their exclusion.

RAI 2.3.3.23-1 License renewal Drawing LR-SN-13432.19-1 for the Nitrogen Supply System at Location A-3 shows that a 3/8" line penetrates the drywell at penetration X-45. Outside the drywell, the line is identified as fulfilling an intended function according to 10 CFR 54.4(a)(1) or 10 CFR 54.4(a)(3) by being highlighted in green. Inside the drywell, the nitrogen line is not identified as fulfilling an intended function. The line apparently supports the Neutron Monitoring System (NMS). Since the NMS is in the scope of license renewal, it is not clear whether the Nitrogen Supply System functionally supports its operation and therefore should be within the scope of license renewal. Confirm whether the 3/8" nitrogen supply line to the NMS should be excluded from the scope of license renewal.

RAI 2.3.3.26-1 On license renewal Drawing LR-GU-3E-551-21-1000, the existing feedwater sample sink and the existing condensate sample sink are shown to be in the scope of license renewal.

However, sinks are not listed as a component subject to an AMR. Indicate if these sinks are included within a component type that is subject to AMR. If not, justify their exclusion from an AMR.

RAI 2.3.3.27-1 Section 2.4.17 of the LRA states that effluents through the ventilation stack are monitored to ensure that the limits of 10 CFR Part 20, which apply to releases during normal operation, and the limits of 10 CFR Part 100, which apply to accidental releases, are not exceeded. LRA Section 2.3.3.27 states that the stack and turbine building Radioactive Gaseous Effluents Monitoring System (RAGEMS) monitors do not support a license renewal intended function and are not included in the scope of license renewal. The above two statements appear to be contradictory. Clarify this apparent discrepancy, and indicate if the ventilation stack radiation monitors are within the scope of license renewal.

RAI 2.3.3.32-1 Note 5 on license renewal Drawing LR-GE-148F444 states that the inner tube of sample cooler (at Location H-8) is evaluated with the reactor water cleanup system. However, LRA Table 2.3.3.32 does not list sample cooler (tubes) as a component subject to an AMR. Confirm that sample cooler tubes are subject to AMR. If not, justify their exclusion from an AMR.

RAI 2.3.3.35-1 LRA Table 2.3.3.25 lists the component type strainer with the intended function filter and strainer body with the intended function pressure boundary. The radiation monitor duplex strainer is indicated in parenthesis for these intended functions. The following components were found to be within the scope of license renewal according to the boundaries given in the Oyster Creek LRA Section 2.3.3.35. They are indicated as being within scope on the license renewal drawings and serve an intended function, but are not listed in LRA Table 2.3.3.35:

a. Strainers located at F-8 and G-7 on license renewal Drawing LR-BR-2005, Sheet 2 provide a pressure boundary function.
b. Strainer S-3-035 in the seal well at B-3/4 on license renewal Drawing LR-BR-2005, Sheet 2 provides a filtration intended function. The seal well is included as part of the miscellaneous yard structures. However, there is no strainer included in this system.

Confirm that these components are subject to an AMR. If not, justify their exclusion from an AMR.

RAI 2.3.3.37-1 LRA Section 2.3.3.37, (Page 2.3-204, 2nd Paragraph) states that the piping that discharges into the reactor cavity, equipment storage cavity and spent fuel pool is included in the scoping boundary for the spent fuel pool cooling system. However, license renewal Drawing LR-GE-237E756 (at Location E-9) does not highlight the piping and associated diffusers that discharge into the reactor cavity as part of scoping boundary. Clarify this apparent discrepancy.

RAI 2.3.4.3-1 Section 2.3.4.3 of the LRA states that the feedwater system is in scope under 10 CFR 54.4(a)(3) because it is relied upon in safety analyses or plant evaluations to perform a function that demonstrates compliance with fire protection per 10 CFR 50.48. Most of the reactor feedwater system shown on license renewal Drawing LR-BR-2003 is colored in red indicating that it is not required for 10 CFR 50.48. It is not clear which portions of the reactor feedwater system are in scope with 10 CFR 54.4(a)(3) for fire protection functions. Please identify those portions of the reactor feedwater system required for 10 CFR 54.4(a)(3) that have fire protection functions.