ML20170A382

Independent Spent Fuel Storage Installation Updated Decommissioning Safety Analysis Report, DSAR 1.1, Rev. 1, Introduction and Summary

ML20170A382
Person / Time
Site:	Fort Calhoun, 07100256
Issue date:	04/30/2020
From:	Dolton J Omaha Public Power District
To:	Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML20170A380	List: LIC-20-0005, Independent Spent Fuel Storage Installation, Technical Specification Basis ML20170A382 ML20170A383 ML20170A384 ML20170A385 ML20170A387 ML20170A388 ML20170A389 ML20170A390 ML20170A391 ML20170A392 ML20170A393 ML20170A394 ML20170A395 ML20170A396 ML20170A397 ML20170A398 ML20170A399 ML20170A400 ML20170A401 ML20170A402 ML20170A403 ML20170A404 ML20170A405 ML20170A406 ML20170A408 ML20170A409 ML20170A410 ML20170A411 ML20170A412 ML20170A414 ML20170A415 ML20170A416 ML20170A417 ML20170A418 ML20170A419 ML20170A420 ML20170A421 ML20170A422 ML20170A423 ML20170A424 ML20170A425 ML20170A426 ML20170A427 ML20170A428 ML20170A429 ML20170A430 ML20170A431 ML20170A432 ML20170A433 ... further results
References
LIC-20-0005
Download: ML20170A382 (3)

Text

Page 1 of 3 DSAR-1.1 Introduction and Summary Introduction Rev 1 Safety Classification: Usage Level:

Safety Information Change No.: EC 69788 Reason for Change: This section is being updated to align with Permanently Defueled Technical Specifications (PDTS)

Preparer: J. Dolton Fort Calhoun Station

DSAR-1.1 Information Use Page 2 of 3 Introduction Rev. 1 Table of Contents

1. INTRODUCTION AND

SUMMARY

.............................................................................. 3 1.1 Introduction ................................................................................................................... 3

DSAR-1.1 Information Use Page 3 of 3 Introduction Rev. 1

1. INTRODUCTION AND

SUMMARY

1.1 Introduction By letters dated June 24 and August 25, 2016, OPPD notified the NRC of its intention to permanently cease power operations at Fort Calhoun Station (FCS) pursuant to 10 CFR 50.82(a)(1)(i). On October 24, 2016, OPPD permanently ceased power operations at FCS (References 1-13, 1-14).

Pursuant to 10 CFR 50.82(a)(1)(ii), OPPD certified to the NRC that as of November 13, 2016, all fuel had been permanently removed from the FCS reactor vessel and had been placed into the spent fuel pool. The letter acknowledged that upon docketing the certifications for permanent cessation of operations and permanent removal of fuel from the reactor vessel, the 10 CFR Part 50 license no longer authorized operation of the reactor or emplacement or retention of fuel in the reactor vessel (Reference 1-15).

By letter from NRC (J. Kim) to OPPD (M. Fisher) Fort Calhoun Station, Unit 1 -

Issuance of Amendment Re: Revised Technical Specifications to Align to Those Requirements for Decommissioning Dated March 6, 2018 (NRC-18-011), OPPD was granted Permanently Defueled Technical Specifications (PDTS). PDTS removed all sections of operating plant TS that no longer apply during the decommissioning process.

Based on the above, the Updated Safety Analysis Report (USAR) is being updated as the Defueled Safety Analysis Report, or DSAR. Prior to permanent removal of fuel, the revised Final Safety Analysis Report, referred to as USAR, was submitted as required under 10 CFR Part 50.71(e), effective July 22, 1980. The original Final Safety Analysis Report was submitted in support of the application by the Omaha Public Power District, (OPPD), for a license pursuant to Section 104b of the Atomic Energy Act, 1954, to operate the Fort Calhoun Station Unit No. 1, (AEC Docket 50-285, Construction Permit CPPR-41).

This report provided pertinent technical information in accordance with the requirements set forth under Title 10 of the Code of Federal Regulations, Part 50, (10 CFR Part 50) and information and analyses submitted to the NRC or prepared as a result of NRC requirements. The plant began commercial operation on September 26, 1973. Prior to decommissioning, the nuclear steam supply system (NSSS) was of the pressurized water type. It was similar in design to several facilities which began operation or were under review by the U.S. Atomic Energy Commission at the time the plant was pursuing its original operating license. A license was requested to operate the facility at power levels up to and including 1420 core thermal megawatts (MWt) which corresponded to a turbine-generator output of 481 MWe. The license was then amended to allow operation at power levels up to and including 1500 core thermal megawatts (MWt) which corresponded to a turbine-generator output of nominal 533.7 MWe at 0.90 power factor.