ML15351A421
| ML15351A421 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/17/2015 |
| From: | Jeffrey Whited Plant Licensing Branch II |
| To: | Wasik C Duke Energy Carolinas |
| Whited, Jeffrey, NRR/DORL/LPLII-1 | |
| References | |
| CAC MF7130, CAC MF7131, CAC MF7132 | |
| Download: ML15351A421 (1) | |
Text
1 Whited, Jeffrey From:
Whited, Jeffrey Sent:
Thursday, December 17, 2015 2:44 PM To:
Wasik, Christopher J (Christopher.Wasik@duke-energy.com)
Cc:
Haile, David Carroll (David.Haile@duke-energy.com); Hall, Randy
Subject:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - ACCEPTANCE FOR REVIEW OF RELIEF REQUEST ON-GRR-01(CAC NOS. MF7130, MF7131 AND MF7132)
SUBJECT:
OCONEE NUCLEAR STATION, UNITS 1, 2 AND 3 - ACCEPTANCE FOR REVIEW OF RELIEF REQUEST ON-GRR-01 CODE CASE OMN-20 (CAC NOS. MF7130, MF7131 AND MF7132)
Mr. Wasik:
By letter dated November 23, 2015 (ADAMS Accession No. ML15335A068), Duke Energy Carolinas, LLC (the licensee), requested relief from the frequency specification requirements of the American Society of Mechanical Engineers, Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) by utilizing the alternate frequencies specified in Code Case OMN-20, for the Oconee Nuclear Station, Units 1, 2 and 3. The licensee is requesting relief pursuant to 10 CFR 50.55a(z)(2) on the basis that complying with frequencies as specified in the OM Code would result in a hardship without a compensating increase in the level of quality and safety.
Pursuant to 10 CFR 50.55a(z), alternatives to the requirements of paragraph 10 CFR 50.55a(g) may be used, when authorized by the NRC, if the licensee demonstrates that: (1) the proposed alternative provides an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
In accordance with NRC's process as described in LIC-109, "Acceptance Review Procedures," the NRC staff has performed an acceptance review of the relief request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
The NRC staff has concluded that the subject relief request does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed relief request in terms of regulatory requirements and the protection of public health and safety and the environment. If needed, the NRC staff may request additional information to complete its technical review.
If you have any questions, please contact me at (301) 415-4090.
Sincerely, JeffreyWhited ProjectManager PlantLicensingBranchII1 DivisionofOperatingReactorLicensing OfficeofNuclearReactorRegulation U.S.NuclearRegulatoryCommission (301)4154090 jeffrey.whited@nrc.gov