ML17251A161
| ML17251A161 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/31/2017 |
| From: | Reising R Duke Energy Florida |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17251A141 | List: |
| References | |
| 3F0817-03 | |
| Download: ML17251A161 (6) | |
Text
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~ ENERGY August 31, 2017 3F0817-03 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428 Docket 72-1035 Docket 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.71(e)
Subject:
Crystal River Unit 3 - Final Safety Analysis Report - August 2017
Reference:
- 1. CR-3 to NRC letter, "Crystal River Unit 3 - Certification of Permanent Cessation of Power Operations and that Fuel Has Been Permanently Removed from the Reactor," dated February 20, 2013. (ADAMS Accession No. ML13056A005)
Dear Sir:
- 2. CR-3 to NRC Letter, "Crystal River Unit 3 - Final ~afety Analysis Report, Revision 38, and 10 CFR 50.59 Report, dated May 25, 2016 (ADAMS Accession No. ML16172A182) 1 In accordance with 10 CFR 50.71(e), Duke Energy Florida, LLC (DEF), hereby submits Revision Oto the Crystal River Unit 3 (CR-3) Defueled Safety Analysis Report (DSAR). One CD-ROM is enclosed to the Document Control Desk and one CD-ROM copy is being sent to the Regional Administrator (Region I). The CR-3 NRC Project Manager will also receive one CD-ROM. This revision replaces the previous revision of the Final Safety Analysis Report (FSAR) in its entirety.
Also included in this submittal is the 10 CFR 50.71(e) update of the FSAR containing all changes to the FSAR since reference 1 was submitted. FSAR text changes are indicated by revision bars on the outside right border of each page. The FSAR revision includes material which describes the organization, modifications, system abandonments and other changes to CR-3 that have been implemented as of July 31, 2017. As required by 10 CFR 50.71(e), a summary of changes made in FSAR, Revision 41 is provided in Attachment 1 (8 changes total).
One of these changes was completed after the associated exemption was approved to assure no Quality Assurance commitments would be reduced.
No new regulatory commitments are made in this letter.
If you have any questions regarding this submittal, please contact Mr. Phil Rose, Nuclear Regulatory Affairs, at (352) 563-4883.
I declare under penalty of perjury that the forgoing is true and correct. Executed on August 31, 2017.
U. S. Nuclear Regulatory Commission 3F0817-03 Sincerely, Ronald R. Reising, Senior Vice President Operations Support RRR/par. ~& FSAR Revision 41 Change Summary Description Defueled Safety Analysis Report (DSAR) xc:
Regional Administrator, Region I NMSS Project Manager Page 2 of 2
DUKE ENERGY FLORIDA, LLC CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302172-1035 LICENSE NUMBER DPR-72 ATTACHMENT 1 FSAR REVISION 41 CHANGE
SUMMARY
DESCRIPTION
U. S. Nuclear Regulatory Commission 3F0817-03 FSAR REVISION 41 CHANGE
SUMMARY
DESCRIPTION Page 1 of 2 The Final Safety Analysis Report (FSAR) revision reflects plant modifications, system abandonment activities, and information and analyses that constitute changes to the FSAR since the publication of FSAR Revision 38. Applicable figures and tables were included in these changes but were not individually identified. One change to the FSAR has been made as the result of License Amendments. As part of implementation of License Amendments No. 248, 250, 251, 252, and 254, FSAR changes were not made as they did not reflect any FSAR described plant change. Amendment numbers 253 and 255 have not been implemented as of this date as they are tied to a notification of removal of all spent fuel from the spent fuel pool.
This FSAR revision includes changes made to incorporate the following:
A. Changes to plant engineering, programs, and revisions to analyses:
FSAR Change Package 2012-02: This change revised FSAR Chapter 1, Introduction
- and Summary, Figure 1-16; Chapter 5 Containment Systems and Other Special Structures, Table 5-5 and Section 5.1; Chapter 9, Auxiliary and Emergency Systems, Section 9.6; and Chapter 11, Radioactive Waste and Radiation Protection, Figure 11-8, to add discussion and update Tables and Figures to reflect the new Auxiliary Building crane that will be used in Independent Spent Fuel Storage Installation (ISFSI) loading activities. The new Auxiliary Building Crane is designed and constructed to be single failure proof and meets the requirements of ASME NOG-1, with approved exceptions.
FSAR Change Package 2016-07: This change revised FSAR Chapter 9, Auxiliary and Emergency Systems, Section 9.6; to revise the operational requirements regarding storage of non-fuel special nuclear material (SNM).
The quantities referenced were based on 10 CFR 71.53, which has since been withdrawn. The definition of critical mass from 10 CFR 70.4 is now being used.
FSAR Change Package 2016-08: This change revised FSAR Chapter 9, Auxiliary and Emergency Systems, Section 9.6; to discuss the fuel that was purchased for the next fuel cycle (Cycle 17) but never irradiated. Duke Energy Florida sold the fuel and needed to ship it off.
This change was to add discussion that would permit removing non-irradiated fuel from the spent fuel pool and shipping it offsite, since this was an activity never before performed at CR-3.
FSAR Change Package 2017-04: This change revised the Fire Brigade make-up from three (3) members down to two (2) and increased reliance on offsite local fire departments for fire response, due to the decommissioning status of the Plant and the associated decreased risk.
The new fire brigade consists of the fire team leader (manned by the Emergency Response Coordinator) and one fire brigade team member that is also a qualified plant operator. The evaluations performed demonstrated that the new. two person fire brigade would still be able to perform all duties and functions of a fire brigade as addressed in 10 CFR 50.48(f) and Regulatory Guide 1.191. This change affected FSAR Chapter 7, Instrumentation and Controls, Section 7.4, Operating Control Stations and FSAR Chapter 9, Auxiliary and Emergency Systems, Section 9.8, Plant Fire Protection Program.
FSAR Change Package 2017-08:
This change revised FSAR Chapter 3, Reactor, Sections 3.1 and 3.2 to discuss the option of re-caging distorted fuel assemblies that were suspected of being too bowed and/or twisted to easily fit into a dry shielded canister storage cell for storage on the ISFSI pad. This is an activity to be performed in
U.S. Nuclear Regulatory Commission 3F0817-03 Page 2 of 2 the spent fuel pool and entails the removal of all fuel pins from the distorted assembly one at a time and placing them in a new cage that meets the form, fit, and function as the original cage.
FSAR Change Package 2017-09: This change revised FSAR Chapter.1, Introduction and Summary, Section 1.1; and Chapter 9, Auxiliary and Emergency Systems, Section 9.6, to add a discussion of the ISFSI. This is a brief description that identified an ISFSI has been constructed on site, whose and which storage system is being used and the location of the 10 CFR 72.212 evaluation.
B. Several editorial and clarification changes were made throughout the document.
Each change was considered for 10 CFR 50.59 applicability using Crystal River Unit 3 and Duke Energy procedures:
FSAR Change Package 2017-07: This change was an editorial change to correct the revision numbers for a specific FSAR figure (Figure 1-26, sheets 1 and 2) identified in the list of effective pages for Chapter 1, Introduction and Summary.
The revision number of this figure had changed in the past, but was not updated on the list of effective pages.
C. Quality Assurance Program changes that did not reduce commitments.
FSAR Change Package 2017-03: This change is an administrative change to document NRC approval of an exemption that permitted removal and destruction of plant records no longer required due to decommissioning. This change affected FSAR Chapter 1, Introduction and Summary, Section 1.7, Quality Program (Operational). The justification for this change stated that 10 CFR 50.54(a) was not required since the NRC approved the change in an exemption request.
The exemption permitted the elimination of requirements to maintain records that are no longer necessary due to the shutdown and permanently defueled condition of the plant.
Specifically, records associated with systems, structures, or components that are no longer in the licensing bases of the plant and were appropriately removed under an approved change process (10 CFR 50.90 or 10 CFR 50.59) no longer have to be retained.
DUKE ENERGY FLORIDA, LLC CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302172-1035 LICENSE NUMBER DPR-72 ATTACHMENT 2 DEFUELED SAFETY ANALYSIS REPORT (DSAR)
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