ML14083A414
| ML14083A414 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/25/2014 |
| From: | Ellen Brown Plant Licensing Branch III |
| To: | Harkness E FirstEnergy Nuclear Operating Co |
| Eva Brown, NRR/DORL 415-2315 | |
| References | |
| TAC MF3197 | |
| Download: ML14083A414 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Ernest J. Harkness Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY -A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 March 25, 2014
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -ACCEPTANCE REVIEW CONCERNING ALTERNATIVE ACCIDENT SOURCE TERM DESIGN BASES (TAC NO. MF3197)(L-13-306)
Dear Mr. Harkness:
By application dated December 6, 2013, as supplemented by a letter dated February 27, 2014 (Agencywide Document Access and Management System (ADAMS) Accession Nos.
ML13343A013 and ML14059A221, respectively), FirstEnergy Nuclear Operating Company (FENOC, the licensee) submitted a license amendment request (LAR) for the Perry Nuclear Power Plant. The proposed amendment would revise the Updated Safety Analyses Report (USAR) to reflect updated radiological calculations using an alternative accident source term from the applicable design bases event and to revise the technical specification (TS) definition of DOSE EQUIVALENT IODINE-131. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this LAR. 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.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
If you have any questions, please contact Ms. Eva Brown, at (301) 415-2315.
Docket No. 50-440 cc: Distribution via Listserv Sincerely, IRA/
Eva A. Brown, Senior Project Manager Plant Licensing 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ML14083A414 NRR-106 OFFICE LPLII-2/PM LPLIII-2/LA LPLIII-2/BC NAME EBrown SRohrer TTate DATE 3/25/14 3/25/14 3/25/14