ML17222A195
| ML17222A195 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/10/2017 |
| From: | Mahesh Chawla Plant Licensing Branch III |
| To: | Coffey R Point Beach |
| Chawla M | |
| References | |
| CAC MF9859, CAC MF9860 | |
| Download: ML17222A195 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Robert Coffey Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241 August 10, 2017
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1AND2-SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: ADOPTION OF EMERGENCY ACTION LEVEL SCHEME PURSUANT TO NEI 99-01, REVISION 6 (CAC NOS. MF9859 AND MF9860)
Dear Mr. Coffey:
By letter dated June 23, 2017, NextEra Energy Point Beach, LLC, (NextEra) (the licensee) submitted a license amendment request (LAR) for Point Beach Nuclear Plant (PBNP), Units 1 and 2. The proposed LAR would revise the Emergency Plan for PBNP to adopt the Nuclear Energy lnstitute's (NEl's) revised emergency action level (EAL) scheme described in NEI 99-01, Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors," which has been endorsed by the NRC.
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 (10 CFR), an amendment to the license (including the technical specifications) 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 the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed LAR in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that the licensee supplement the application to address the information requested in the enclosure by August 21, 2017. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised
of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated time frame in this letter were discussed with your representative, Mr. Eric Schultz, Point Beach Licensing Manager, during a teleconference held on August 2, 2017 to discuss the subject information.
If you have any questions, please contact me at (301) 415-8371 or Mahesh.chawla@nrc.gov.
Docket Nos. 50-266 and 50-301
Enclosure:
As stated cc w/encl: Distribution via Listserv Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUPPLEMENTAL INFORMATION NEEDED AMENDMENT REQUEST - ADOPTION OF EMERGENCY ACTION LEVEL SCHEME PURSUANT TO NUCLEAR ENERGY INSTITUTE 99-01, REVISION 6 NEXTERA ENERGY POINT BEACH. LLC POINT BEACH NUCLEAR PLANT. UNIT NOS 1 AND 2 DOCKET NOS. 50-266 AND 50-301 Concerning Radiological Effluent Calculation values, the licensee provided a cover sheet and selected pages from the calculation. No calculations, assumptions, or explanations are provided that could be used to determine that the proposed radiation values, which are notably different from the licensee's current values, are reasonable. Additionally, no calculations were provide to support the containment radiation monitor setpoints for fission product barrier threshold values.
To complete the acceptance review, following supplemental information is required:
- 1. Calculations that support the Radiological Effluent values for the proposed EAL scheme.
- 2. Calculations that support the Fission Product Barrier containment radiation threshold values.
Enclosure
ML17222A195 OFFICE NRR/DORULPL3/PM NRR/DORULPL3/LA NAME MChawla SRohrer DATE 8/10/2017 8/10/2017 OFFICE NRR/DORULPL3/BC NRR/DORULPL3/PM NAME DWrona MChawla DATE 8/10/2017 8/10/2017