NL-04-1218, Units I and 2 - Application for License Renewal - Supplemental Information
| ML042010294 | |
| Person / Time | |
|---|---|
| Site: | Farley  (NPF-002, NPF-008) |
| Issue date: | 07/09/2004 |
| From: | Stinson L Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-04-1218 | |
| Download: ML042010294 (7) | |
Text
I L M. Stinson (Mike)
Vice President Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.5181 Fax 205.992.0341 SOUTHERNAM COMPANY Energy to Serve YourWorld' July 9, 2004 Docket Nos.:
50-348 50-364 NL-04-1218 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Joseph M. Farley Nuclear Plant, Units I and 2 Application for License Renewal - Supplemental Information Ladies and Gentlemen:
In response to NRC Staff requests, this letter provides supplemental information to aid in the review of the Joseph M. Farley Nuclear Plant, Units I and 2, Application for License Renewal. Descriptions of the specific requests and the SNC responses are provided in the Enclosure.
Mr. L. M. Stinson states he is a vice president of Southern Nuclear Opemting Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and to the best of his knowledge and belief, the facts set forth in this letter are true.
If you have any questions, please contact Charles Pierce at 205-992-7872.
Respectfully submitted, SOUTHERN NUCLEAR OPERATING COMPANY L. M. Stinson Sworn to and subscribed before me this W I day of J aA&0
.. 2004.
Notary Public My commission expiresi: (IC -. -7 I
I I,.
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U. S. Nuclear Regulatory Commission NL-04-1218 Page 2 LMS/JAM/slb
Enclosure:
Joseph M. Farley Nuclear Plant, Units I and 2 Application for License Renewal - Supplemental Information cc:
Southern Nuclear Operating Company Mr. J. B. Beasley Jr., Executive Vice President Mr. D. E. Grissette, General Manager - Plant Farley Document Services RTYPE: CFA04.054; LC# 14081 U. S. Nuclear Regulatorv Commission Ms. T. Y. Liu, License Renewal Project Manager Dr. W. D. Travers, Regional Administrator Mr. S. E. Peters, NRR Project Manager - Farley Mr. C. A. Patterson, Senior Resident Inspector - Farley Alabama Department of Public Health Dr. D. E. Williamson, State Health Officer
NL-04-1 218 ENCLOSURE Joseph M. Farley Nuclear Plant, Units 1 and 2 Application for License Renewal Supplemental Information E-1
Enclosure NL-04-1218 Supplemental Information - Atmospheric Vents on the Refueling Water Storaqe Tanks, Condensate Storage Tanks, and Reactor Makeup Water Storage Tanks During the recent NRC Region II scoping and screening inspection, inspectors noted that atmospheric vents on several tanks were not included in the scope of license renewal. SNC agreed to include the vents for the refueling water storage tanks, condensate storage tanks, and the reactor makeup water storage tanks in the scope of license renewal. (Refer to NRC inspection report 50-348/2004-007, 50-364/2004-007 dated June 22, 2004.)
The following table lists the tanks and the applicable parts of the LRA:
Tank (vent)
LRA Scoping Section LRA AMR Table Refueling Water Sect. 2.3.2.3 -
Emergency Core Table 3.2.2-3 Storage Tanks Cooling System (RWSTs)
Reactor Makeup Sect. 2.3.3.23 - Reactor Makeup Table 3.3.2-23 Water Storage Water Storage Tanks (RMWSTs)
System Condensate Sect. 2.3.4.4 -
Auxiliary Feedwater Table 3.4.2-4 Storage Tanks System (CSTs)
The vents are considered integral subparts of the tanks and consequently are lumped into the existing "tank" component type. Therefore, the components subject to an aging management review (AMR) tables in the corresponding LRA scoping sections are unaffected.
For the refueling water storage tanks, the uair/gas (wetted)" environment is conservatively applied to the tank vents since they may be exposed to moisture (condensation) from high humidity in the tank (as a result of the open water level). For the condensate storage tanks and reactor makeup water storage tanks which have internal diaphragms, the 'air/gase (non-wetted) environment is applied to these vents because they are not exposed to high moisture (humidity) from the tank's water contents due to the protective internal diaphragm.
The aging management review summary tables in the LRA should have included the following additional material environment combinations for the tanks as a result of bringing the tank vents into scope:
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Enclosure NL-04-1218 Table 3.2.2-3 Engineered Safety Features, Emergency Core Cooling System -
Summary of Aging Management Review Component Type Aging Effect NUREG-1801 GALL Intended Material Environment Requiring Aging Management Volume 2 Table 1 Reference Function Management Programs Item Item Notes Refueling Pressure Stainless Air/gas Loss of One Time Inspection G
Water Storage Boundary Steel (wetted)
Material Program Tank (includes tank vent)
V.D1.8.3 Table 3.4.2-4 Steam and Power Conversion Systems, Auxiliary Feedwater System -
Summary of Aging Management Review Component Type Aging Effect NUREG-1801 GALL Intended Material Environment Requiring Aging Management Volume 2 Table 1 Reference Function Management Programs Item Item Notes Condensate Pressure Carbon Air/Gas (non-Loss of One-Time Inspection G
Storage Tank Boundary Steel wetted)
Material Program (includes tank vent)
VIII.G.4. 1 Table 3.3.2-23 Auxiliary Systems, Reactor Makeup Water Storage System - Summary of Aging Management Review Component Type Aging Effect NUREG-1801 GALL Intended Material Environment Requiring Aging Management Volume 2 Table 1 Reference Function Management Programs Item Item Notes Reactor Pressure Stainless Air/Gas (non-None None Required J
Makeup Water Boundary Steel wetted)
Storage Tank (includes tank vent)
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Enclosure NL-04-1 218 RAI 3.6.2 Supplemental Information SNC responded to RAI 3.6.2-5 in SNC letter NL-04-0678 dated April 22, 2004. After review of the SNC response, the NRC staff requested supplemental information via a follow-up question. The following question was originally identified by the staff as a follow-up to RAI 3.6.2-2 but was clarified as being associated with RAI 3.6.2-5 during a telephone conference on June 10, 2004:
The applicant has stated in its RAI response that Cable Bus will be in the Non-EQ Cable Program. The staff requests the applicant indicate which part of that program. Because the cable in the Cable Bus is not accessible, it is expected to be treated as non-accessible medium voltage cable. The LRA Table 3.6.2-1 has it listed in the low voltage cable program.
Response
The FNP Cable Aging Management Program is made up of NUREG-1801 Aging Management Programs XL.E1, XL.E2, and XL.E3. Each NUREG-1801 program applies to a different cable aging issue. All cables, regardless of voltage rating or application, are included in the XL.E1 program even if they are affected by an aging issue covered by one of the other programs, since this program requires plant-wide inspections.
The cable in the Cable Bus is in the XL.E1 portion of the Non-EQ Cables Program as reflected in LRA Table 3.6.2-1. The bus cables exit the bus duct enclosures in the low voltage switchyard and approximately six feet of the cables are exposed where they connect to the start-up auxiliary transformers. This portion of the cables will be visually inspected per the Non-EQ Cables Program.
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Enclosure NL-04-1218 Supplemental Information to LRA Section 3.1.2.2.4 In a teleconference on June 23, 2004, the NRC staff requested supplemental information in reference to LRA Section 3.1.2.2.4 (and the corresponding item 7 in LRA Table 3.1.1) on ASME Class 1 small bore piping inspections to be performed under the recently approved Risked Informed Inservice Inspection (RI-ISI) Program for Farley Nuclear Plant. The staff specifically requested that SNC identify any ASME Class 1 small bore piping weld locations that will be volumetrically examined under the RI-ISI Program.
The FNP Unit 1 and Unit 2 RI-ISI Program includes volumetric examination of one ASME Class 1 small bore (defined as piping less than 4-inch nominal pipe size) segment per unit. Segment 1 (2)RC-024A is the 2-inch drain line that tees off of the 3-inch normal letdown line in each unit. The 2-inch circumferential butt weld at the tee in each unit is scheduled for ultrasonic examination under the RI-ISI Program.
As stated in LRA Section 3.1.2.2.4, the One-Time Inspection (OTI) Program will provide for examinations of small bore (< 4-inch NPS) ASME Class 1 piping to confirm cracking (due to thermal cycling or stress corrosion cracking) is not occurring in these lines. As a clarification, examinations performed under the RI-ISI Program that permit inspection of the inside surfaces (e.g., volumetric examination) of the small bore ASME Class 1 piping will be included as part of the representative sample for the OTI Program as applicable.
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