ML16313A016
| ML16313A016 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 11/30/2016 |
| From: | Mahesh Chawla Plant Licensing Branch III |
| To: | Vehec T Nextera Energy |
| Chawla M | |
| References | |
| CAC MF6618 | |
| Download: ML16313A016 (5) | |
Text
Mr. Thomas A. Vehec Vice President NextEra Energy UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 30, 2016 Duane Arnold Energy Center 3277 DAEC Road Palo, IA 52324-9785
SUBJECT:
DUANE ARNOLD ENERGY CENTER - CORRECTION OF ERRORS IN SAFETY EVALUATION ASSOCIATED WITH LICENSE AMENDMENT NO. 295 (CAC NO. MF6618)
Dear Mr. Vehec:
By letter dated August 18, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16153A091), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 295 to Renewed Facility Operating License No. DPR-49 for the Duane Arnold Energy Center (DAEC).
The amendment revised the value of reactor steam dome pressure specified within DAEC technical specifications (TSs) Section 2.1.1, "Reactor Core SLs [Safety Limits], to resolve a Title 1 O of the Code of Federal Regulations (CFR), Part 21 condition. The Part 21 condition was concerning a potential to momentarily violate TSs 2.1.1.1 and 2.1.1.2 during a pressure regulator failure maximum demand (open) transient.
On September 15, 2016, the NRC was notified by NextEra Energy Duane Arnold, LLC (the licensee), that errors had been identified in the safety evaluation (SE) enclosed in the August 18, 2016, letter. The following corrections were made in the SE on page 3.
SE Previous Version Revised Version Description of the Section change 2.2 THERMAL POWER THERMAL POWER shall Replaced < with s shall be < 21. 7 percent be s 21. 7 percent RTP symbol RTP 2.2 2.1.1.2 MCPR-With 2.1.1.2 MCPR-Withthe Replaced > with ~
the reactor steam reactor steam dome symbol dome pressure >686 pressure ~ 686 psig and psig and core flow core flow ~ 10% rated
>10% ratedcoreflow:
core flow:
MCPRshallbe >1.10for MCPR shall be ~ 1.10 for two two recirculation loop recirculation loop operation operation or > 1.12 for or ~ 1.12 for single single recirculation loop recirculation loop operation operation
The NRC staff has determined that these were inadvertent typographical errors and were entirely editorial in nature. The corrections do not change any of the conclusions in the SE associated with the issuance of Amendment No. 295 for DAEC and do not affect the associated notice to the public.
Please find enclosed the replacement page 3 of the SE associated with this amendment. If you have any questions regarding this matter, please contact me at (301) 415-8371.
Docket No. 50-331
Enclosure:
Corrected Safety Evaluation Associated with License Amendment No. 295 cc w/encl: Distribution via ListServ Sincerely, Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ENCLOSURE DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 CORRECTED SAFETY EVALUATION, PAGE 3, ASSOCIATED WITH LICENSE AMENDMENT NO. 295
2.2 Proposed TS Changes
The proposed changes would reduce the reactor steam dome pressure from 785 psig to 686 psig, specified in TS Sls 2.1.1.1 and 2.1.1.2. As a result of this change, the TS Sls 2.1.1.1and2.1.1.2, would read:
2.1.1.1 Fuel Cladding Integrity - With the reactor steam dome pressure< 686 psig or core flow < 10 percent rated core flow:
THERMAL POWER shall be::;; 21.7 percent RTP.
2.1.1.2 MCPR [minimum critical power rate] - With the reactor steam dome pressure
~ 686 psig and core flow ~10% rated core flow:
MCPR shall be ~ 1.10 for two recirculation loop operation or ~ 1.12 for single recirculation loop operation.
The licensee's application also provided revised TS Bases pages to be implemented with the associated TS changes. These pages were provided for information only. Changes to the TS Bases would be made in accordance with the TS Bases Control Program.
2.3 Regulatory Requirements and Guidance The NRC staff considered the following regulatory requirements and guidance documents in its review of the proposed amendment.
10 CFR 50.36, "Technical specifications," provides the regulatory requirements for the content required in the TSs. As stated in 10 CFR 50.36(c)(1 )(i)(A),
Safety limits for nuclear reactors are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity. If any safety limit is exceeded, the reactor must be shut down. The licensee shall notify the Commission, review the matter, and record the results of the review, including the cause of the condition and the basis for corrective action taken to preclude recurrence. Operation must not be resumed until authorized by the Commission."
Compliance with the fuel licensing criteria of 1 O CFR 50, Appendix A, General Design Criterion (GDC) 10, "Reactor design," is achieved by preventing the violation of fuel design limits.
GDC 10 states:
The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits [SAFDLs] are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," provides guidance on the acceptability of the reactivity control systems, the
ML16313A016 OFFICE DORULPL3-1/PM DORULPL3-1/LA NAME MChawla SRohrer DATE 11/8/16 11/8/16 Mahesh Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsRgn3MailCenterResource RecordsAmend Resource MRazzaque, NRR CTilton, NRR KStoedter, R3 CNorton, R3 JSteffes, R3 DSS/STSB/BC DSS/SRXB/BC DORL/LPL3-1/BC AKlein EOesterle DWrona 11/10/16 11/10/16 11/30/16