ML053630240
| ML053630240 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 12/29/2005 |
| From: | Ashley D NRC/NRR/ADRO/DLR/RLRB |
| To: | AmerGen Energy Co |
| Ashley D, NRR/DLR/RLRA, 415-3191 | |
| References | |
| %dam200606, -RFPFR | |
| Download: ML053630240 (10) | |
Text
December 29, 2005 LICENSEE:
AmerGen Energy Company, LLC FACILITY:
Oyster Creek Nuclear Generating Station
SUBJECT:
SUMMARY
OF A TELEPHONE CONFERENCE CALL HELD ON DECEMBER 2, 2005, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (NRC or the staff), and representatives of AmerGen Energy Company, LLC (AmerGen), held a telephone conference call on December 2, 2005, to discuss and clarify the staffs draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application (LRA). The conference call was useful in clarifying the intent of the staffs D-RAIs. provides a listing of the conference call participants. Enclosure 2 contains a listing of the D-RAIs discussed with the applicant, including a brief description on the status of the items.
The applicant had an opportunity to comment on this summary.
/RA/
Donnie J. Ashley, Project Manager License Renewal Branch B Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-219
Enclosures:
As stated cc w/encls: See next page
ML053630240 DOCUMENT NAME: E:\\Filenet\\ML053630240.wpd OFFICE PM:RLRB LA:DLR BC:RLRB (A)
NAME DAshley YEdmonds LLund DATE 12/20/05 12/20/05 12/29/05
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 Licensee AmerGen Energy Company from Donnie J. Ashley dated December 29, 2005
SUBJECT:
SUMMARY
OF A TELEPHONE CONFERENCE CALL HELD ON DECEMBER 2, 2005, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION DISTRIBUTION:
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Enclosure 1 LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALL TO DISCUSS THE OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION December 2, 2005 Participants Affiliations Donnie J. Ashley U.S. Nuclear Regulatory Commission (NRC)
David Shum NRC Rodrigo De La Garza NRC Fred Polaski AmerGen Energy Company, LLC (AmerGen)
John Hufnagel AmerGen Don Warfel AmerGen Mark Miller AmerGen Kim Green Information System Laboratory (ISL)
Cliff Marks ISL DRAFT REQUEST FOR ADDITIONAL INFORMATION (D-RAI)
OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION December 2, 2005 The U.S. Nuclear Regulatory Commission staff (NRC or the staff) and representatives of AmerGen Energy Company, LLC (AmerGen), held a telephone conference call on December 2, 2005, to discuss and clarify the staffs draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station, license renewal application (LRA). The following D-RAIs were discussed during the telephone conference call:
D-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.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 2.3.3.20-1 License renewal Drawing LR-BR-2013, Sheet 7 for the instrument (control) air system, at Location C-2 shows automatic control valves v-6-3313 and v-6-3314 as within the scope of license renewal in accordance with 10 CFR 54.4(a)(1) or 10 CFR 54.4(a)(3) (i.e., highlighted in green). Note 4 is applicable to this piping section implying that it is safety-related. The automatic valves have non-safety-related components and piping shown directly adjacent to them as not within the scope of license renewal (i.e., not highlighted). Similar automatic control valves v-6-3315 and v-6-3316, on license renewal Drawing LR-BR-2013, Sheet 6 at Location F-8 have similar piping shown as within the scope of license renewal in accordance with 10 CFR 54.4(a)(2) (i.e., highlighted in red). Explain the functional differences between the automatic control valve arrangements described above.
Discussion: The LRA Drawing LR-BR-213, Sheet 6 and LRA Page Number 2.1-21 provides clarifying information that explains the functional differences between the valves. The question will be withdrawn.
D-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 NMS 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.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-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 an AMR. If not, justify their exclusion from an AMR.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 2.3.3.27-1 Section 2.3.3.27 of the LRA states that the majority of the radiation monitoring system consists of radiation detectors and associated circuitry, and a boundary description for a mechanical system is not applicable since these components are evaluated as an electrical commodity.
LRA Section 2.5.1.14 implies that the only radiation monitors that are in scope are the two high range radiation monitors installed within the drywell. Identify all of the radiation monitors that are within the scope of license renewal.
Discussion: The answer that the licensee will provide for the Post Accident draft question D-2.3.3.27-2 will also answer this one. This question will be withdrawn.
D-RAI 2.3.3.27-2 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.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI and will be renumbered as RAI 2.3.3.27-1, due to the previous question being withdrawn.
D-RAI 2.3.3.30-1 The following components were found to be within the license renewal scoping boundary for the reactor building floor and equipment drain system, according to information provided in the Oyster Creek LRA. The following components are highlighted on the corresponding LRA drawings, but are not listed as components subject to an AMR in LRA Table 2.3.3.30:
- a. y-strainer No. 116 at Location D-10 on Drawing LR-GE-148F444;
- b. flow indicators FG-168B and FG-168C at D-2 and D-5, respectively, on Drawing LR-GR-148F444; and c.
flow indicator FIS-51 on LR-GE-237E756 at Location C-8.
These components all provide leakage boundaries in accordance with 10 CFR 54.4(a)(2).
Confirm that these components are subject to an AMR. If not, justify their exclusion from an AMR.
Discussion: LRA Drawing LRBR-2001, Sheet 2, Note 8 explains the boundary. The question will be withdrawn.
D-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 an AMR. If not, justify their exclusion from an AMR.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-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, 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.
They provide a pressure boundary function; and
- b. strainer S-3-035 in the seal well at B-3/4 on license renewal Drawing LR-BR-2005, Sheet 2. It 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.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-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 the scoping boundary. Clarify this apparent discrepancy.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-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 for 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.
Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as a formal RAI.
D-RAI 2.3.4.7-1 Section 2.3.4.7 of the LRA states that the turbine is supported by other auxiliary systems, one of which is the mechanical-hydraulic control (MHC) system. The LRA states that the MHC provides hydraulic fluid and mechanical linkage to control certain valves and the reactor pressure through pressure regulators. The system boundary for the main turbine and auxiliary system is stated to be that portion of the system that is located in proximity to equipment performing a safety-related function, and a reference to the license renewal drawings for identification of this boundary is made. Failure of the MHC system could potentially impact safety-related equipment or equipment performing a safety-related function within the vicinity of the MHC system. However, the referenced license renewal drawings do not show the MHC system. Indicate if the MHC or any portion thereof is within the scope of license renewal.
Discussion: The LRA Drawing LR-BR-2014, Sheet 1, Note 4 explains the scoping boundary.
The question will be withdrawn.