ML14049A217
| ML14049A217 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 02/19/2014 |
| From: | Jason Paige Plant Licensing Branch II |
| To: | Henderson K Duke Energy Carolinas |
| Paige, Jason NRR/DORL 415-5888 | |
| References | |
| TAC MF3473, TAC MF3474 | |
| Download: ML14049A217 (7) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 rebruary 19, 2014 Mr. K. Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, SC 29745
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2- PUBLIC NOTICE OF APPLICATION FOR AMENDMENT TO FACILITY OPERATING LICENSE (TAC NOS. MF3473 AND MF3474)
Dear Mr. Henderson:
The enclosed announcement was forwarded to The Herald for publication. This announcement relates to your application dated February 17, 2014, for amendments to Renewed Facility Operating License NPF-35 and to Renewed Facility Operating License NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The proposed amendment would revise Technical Specification 3.3.4 as a result of an inoperable instrumentation function on Unit 2.
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tason C. Paige, Proj:ct ::n~g~;
Piant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-413 and 50-414
Enclosure:
Public Notice cc w/encl: Distribution via Listserv
PUBLIC NOTICE NRC STAFF PROPOSES TO AMEND OPERATING LICENSES AT CATAWBA NUCLEAR STATION, UNITS 1 AND 2 The U.S. Nuclear Regulatory Commission (Commission, NRC) staff has received an application dated February 17, 2014, from Duke Energy Carolinas, LLC (Duke Energy), for an exigent amendment to the operating license for Catawba Nuclear Station, Units 1 and 2, located in York, South Carolina.
The proposed amendments would revise Technical Specification (TS) Table 3.3.4-1, remote Shutdown System Instrumentation and Controls as a result of an inoperable instrumentation function on Unit 2. Table 3.3.4-1 specifies requirements for Function 3.b.,
Decay Heat Removal via Steam Generators (SGs)- Reactor Coolant System (RCS) Cold Leg Temperature- Loop A and Bas "1 per loop". Loop A of this function is presently inoperable on Unit 2 due to a failed resistance temperature detector (RTD). Loop B of this function is operable with a reliable maintenance history. The failed RTD on Loop A cannot be replaced in the present operating mode of Unit 2 (Mode 1). Therefore, Duke Energy is requesting NRC approval to allow Unit 2 to remain in Mode 1 until such time that the failed RTD can be replaced.
The replacement would occur in the next refueling outage or the next outage that would facilitate replacement, whichever occurs first.
On January 31,2014, the Unit 2 RCS Cold Leg Temperature- Loop A was declared inoperable to perform TS required calibration. Following the calibration, but before the function could be declared operable, erractic indications were observed and troubleshooting activities were initiated to determine the cause of the erratic indications. After extensive troubleshooting, it was determined on February 14, 2014, that the loop RTD had failed and required replacement, which would necessitate a unit shutdown.
As discussed in the licensee's application dated February 17, 2014, Duke Energy requested that the proposed amendment be processed by the NRC on an exigent basis in accordance with the provisions of Title 10 of the Code of Federal Regulations ( 10 CFR) paragraph 50.91 (a)(6). Under 10 CFR 50.91 (a)(6)(i)(B), where the Commission finds that exigent circumstances exist, in that a licensee and the Commission must act quickly and that time does not permit the Commission to publish a Federal Register notice allowing 30 days for prior public comment, and it also determines that the amendment involves no significant hazards considerations, the Commission will use local media to provide reasonable notice to the public in the area surrounding a licensee's facility of the licensee's amendment and of its proposed determination that no significant hazards consideration is involved, consulting with the licensee on the proposed media release and on the geographical area of its coverage.
The licensee is basing exigent circumstances on the following: (1) the circumstances leading to the exigency were unforeseen; (2) there was no adverse maintenance history concerning the RTD component; and (3) this remote shutdown system function had previously passed its required TS surveillance and other required testing.
The licensee provided its analysis about the issue of no significant hazards consideration using the standards in 10 CFR 50.92, which means the proposed amendment would not (1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety. The NRC staff has considered the licensee's information and is now making a proposed determination that the amendment involve no significant hazards considerations as explained below.
Operation of Catawba, Units 1 and 2, in accordance with the proposed amendments will not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed amendments do not affect the probability of any accident occurring since the Remote Shutdown System is not an accident initiator or a precursor to the initiation of any analyzed accident. Therefore, there can be no increase in the probability of any accident occurring. The Remote Shutdown System functions to provide an auxiliary means to shut down the unit should the control room become inoperable or uninhabitable. Procedural guidance will ensure that plant operators can compensate for the inoperable Remote Shutdown System function (Reactor Coolant System Cold Leg Temperature- Loop A) while this license amendment is in effect. The risk of extended plant operation with the inoperable function out of service was qualitatively assessed to be low. In addition, the proposed amendments will not affect the performance of any other plant equipment used to mitigate the consequences of an analyzed accident. There will be no significant impact on the source term or pathways assumed in accidents previously evaluated. No analysis assumptions will be violated and there will be no adverse effects on offsite or onsite dose as the result of an accident.
Therefore, the proposed amendments do not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed amendments will not create the possibility of a new or different kind of accident from any previously analyzed. The proposed amendments do not change the methods governing normal plant operation; nor are the methods utilized to respond to plant transients and accidents altered. Procedural guidance will ensure that plant operators appropriately respond to transients and accidents even with the inoperable Remote Shutdown System function. In addition, the proposed amendments will not create the potential for any new initiating transients or accidents to occur in the actual physical plant.
Therefore, the proposed amendments do not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed amendments will not involve a significant reduction in a margin of safety.
Margin of safety is related to the confidence in the ability of the fission product barriers to perform their design functions during and following an accident. These barriers include the fuel cladding, the Reactor Coolant System, and the containment system. The proposed amendments will not challenge the acceptability of any analytical limits under normal, transient, and accident conditions. All applicable design and safety limits will continue to remain satisfied such that the fission product barriers will continue to perform their design functions.
Therefore, the proposed amendments do not involve a significant reduction in a margin of safety.
Following an initial review of this application, the requested amendments have been evaluated against the standards in 10 CFR 50.92 and the NRC staff has made a proposed determination that the requested amendments involve no significant hazards considerations.
The changes do not significantly increase the probability or consequences of any accident previously considered, nor create the possibility of an accident of a different kind, nor significantly decrease any margin of safety.
Comments on the proposed determination of no significant hazards consideration may be ( 1) telephoned to Mr. Robert J. Pascarelli, Chief, Plant Licensing Branch 2-1 , by collect call to 301-415-6603, or by facsimile to 301-415-2102, (2) e-mailed to Robert. Pascarelli@ nrc.gov, or (3) submitted in writing to the Chief, Rules, Announcements and Directives Branch, Division of Administrative Services, Office of Administration, Mail Stop: 3WFN-06-A44MP, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. All comments received by 7:30 a.m. on February 26, 2014, will be considered in reaching a final determination. A copy of the
application may be examined electronically through the NRC's Agencywide Documents Access and Management System (ADAMS) in the NRC Library at http://www.nrc.gov/reading-rm/adams.html and at the Commission's Public Document Room (PDR), located at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1-800-397-4209, or 301-415-4737, or by e-mail to pdr.resource@nrc.gov.
If the NRC decides to approve the requested amendments, it will publish notices of issuance under 10 CFR 2.1 06. The NRC will provide a hearing after issuance, if one has been requested by a person who satisfies the provisions for intervention specified in 10 CFR 2.309.
- ML14049A217 OFFICE NRR/DORL!LPLX2-1 /PM NRR/DORL!LPL2-1/LA OGC NAME JPaige SFigueroa DRoth DATE 2/18/14 2/18/14 2/19/14 OFFICE NRR/DORL!LPL2-1/BC NRR/DORL!LPL2-1 /PM NAME RPascarelli JPaige DATE 02/19/14 02/19/14