ML16139A164
| ML16139A164 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 05/26/2016 |
| From: | Jeffrey Whited Plant Licensing Branch II |
| To: | Henderson K Duke Energy Carolinas |
| Whited J, NRR, DORL 415-4090 | |
| References | |
| CAC MF6166, CAC MF6167 | |
| Download: ML16139A164 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Kelvin Henderson Site Vice President Catawba Nuclear Station Duke Energy Carolinas, LLC 4800 Concord Road York, NC 297 45 May 26, 2016
SUBJECT:
CATAWBA NUCLEAR STATION, UNITS 1 AND 2 - CORRECTION TO SAFETY EVALUATION PAGE FOR AMENDMENT NOS. 279 AND 275 RE: ISSUANCE OF LICENSE AMENDMENTS REGARDING EMERGENCY ACTION LEVEL SCHEME CHANGE (CAC NOS. MF6166 AND MF6167)
Dear Mr. Henderson:
By letter dated April 18, 2016, 1 the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 279 to Renewed Facility Operating License (RFOL) No. NPF-35 and Amendment No. 275 to RFOL No. NPF-52 for the Catawba Nuclear Station, Units 1 and 2, respectively. The associated safety evaluation (SE) contained a typographical error.
Specifically, the error consisted of an omission of part of the quoted regulation from Title 1 O of the Code of Federal Regulations (10 CFR), Section 50.47, "Emergency plans,"
10 CFR 50.47(a)(1 )(i). The error occurred on page 2 of the associated SE.
A corrected copy of page 2 of the associated SE is enclosed. This correction does not change any of the conclusions in the SE associated with the license amendments.
1 Agencywide Documents Access and Management System Accession No. ML16082A038.
We apologize if this error has caused any inconvenience. If you have any questions regarding this matter, please contact me at (301) 415-4090 or by e-mail at jeffrey.whited@nrc.gov.
Docket Nos. 50-413 and 50-414
Enclosure:
Corrected SE page cc w/enclosure: Distribution via Listserv Sincerely, Jeffrey A. Whited, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ENCLOSURE Catawba Nuclear Station, Units 1 and 2 Corrected Page 2 of the Safety Evaluation for Amendment Nos. 279 and 275 Dated April 18, 2016
... no initial operating license for a nuclear power reactor will be issued unless a finding is made by the NRC that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.
Section 50.47(b) to 10 CFR Part 50 establishes the standards that the onsite and offsite emergency response plans must meet for the NRC staff to make a positive finding that there is reasonable assurance that adequate protective measures can and will be taken in the event of a radiological emergency.
Planning standard (4) of Section 50.47(b) to 10 CFR Part 50 requires that onsite and offsite emergency response plans meet the following:
A standard emergency classification and action level scheme, the bases of which include facility system and effluent parameters, is in use by the nuclear facility licensee, and State and local response plans call for reliance on information provided by facility licensees for determinations of minimum initial offsite response measures.
Section 50.47(b)(4) to 10 CFR Part 50 emphasizes the use of a standard emergency classification and action level scheme, assuring that implementation methods are relatively consistent throughout the industry for a given reactor and containment design while simultaneously providing an opportunity for a licensee to modify its EAL scheme as necessary to address plant-specific design considerations or preferences.
Section IV.B of Appendix E, "Emergency Planning and Preparedness for Production and Utilization Facilities," to 10 CFR Part 50, states, in part, that:
The means to be used for determining the magnitude of, and for continually assessing the impact of, the release of radioactive materials shall be described, including emergency action levels that are to be used as criteria for determining the need for notification and participation of local and State agencies, the Commission, and other Federal agencies, and the emergency action levels that are to be used for determining when and what type of protective measures should be considered within and outside the site boundary to protect health and safety. The emergency action levels shall be based on in-plant conditions and instrumentation in addition to onsite and offsite monitoring. By June 20, 2012, for nuclear power reactor licensees, these action levels must include hostile action that may adversely affect the nuclear power plant.
2.2 Guidance The EAL development guidance was initially established in NRC Generic Letter (GL) 79-50, "Emergency Plans Submittal Dates," dated October 10, 1979 (Reference 5), and was subsequently revised in NUREG-0654/FEMA-REP-1, Rev. 1, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants," dated November 1980 (Reference 6), which was endorsed as an approach for the development of an EAL scheme by NRC Regulatory Guide (RG) 1.101, Rev. 2, "Emergency Planning and Preparedness for Nuclear Power Reactors," October 1981 (Reference 7).
ML16139A164 LPL2-1 R/F RidsNrrDorlDpr Resource RidsNrrPMCatawba Resource RidsNrrLALRonewicz Resource RecordsAmend Resource RidsNrrOd Resource OFFICE DORL/LPL2-1/PM DORL/LPL2-1/LA DORL/LPL2-1/BC DORL/LPL2-1 /PM NAME JWhited LRonewicz MMarkley JWhited (MHenderson for)
DATE 05/25/16 05/25/16 05/26/16 05/26/16