ML110870682
| ML110870682 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 03/28/2011 |
| From: | Wang A Plant Licensing Branch IV |
| To: | Baldwin T, Soenen P Pacific Gas & Electric Co |
| Wang, A B, NRR/DORL/LPLIV, 415-1445 | |
| References | |
| TAC ME5713, TAC ME5714 | |
| Download: ML110870682 (2) | |
Text
From:
Wang, Alan Sent:
Monday, March 28, 2011 11:41 AM To:
Baldwin, Thomas (DCPP); Soenen, Philippe R Cc:
Lent, Susan; Burkhardt, Janet; Polickoski, James
Subject:
Acceptance of Diablo Canyon Power Plant (DCPP) License Amendment Reqest Regarding Main Steam Safety Valves (ME5713 and ME5714)
Tom and Philippe, By letter dated February 17, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110480870), Pacific Gas and Electric Company. (PG&E, the licensee) requested an amendment to the Facility Operating License for the DCPP. The proposed license amendment request (LAR) would revise Technical Specification (TS) 3.7.1, "Main Steam Safety Valves (MSSVs)," Table 3.7.1-1, "Maximum Allowable Power Range Neutron Flux High Setpoint With Inoperable MSSVs," and the TS Bases for the MSSVs. This LAR proposes to remove a one-time note listed in TS Table 3.7.1-1, specific to Unit 2 Cycle 15, that is no longer applicable or needed. This LAR also proposed to revise the TS Bases B 3.7.1 to reflect a new analysis methodology for establishing the reduced Power Range (PR) neutron flux high setpoint for one inoperable MSSV as listed in Table 3.7.1-1. There is no proposed change to the PR neutron flux high setpoint as the value of 87 percent Rated Thermal Power (RTP) listed in TS Table 3.7.1-1 for one inoperable MSSV will remain the same.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment 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.
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 it does provide technical information in sufficient detail to enable the staff to proceed with 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. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-1445.
Alan Wang Project Manager (Diablo Canyon Power Plant)
Nuclear Regulatory Commission Division of Operating Reactor Licensing Alan.Wang@NRC.gov
Tel: (301) 415-1445 Fax: (301) 415-1222