0CAN061901, Annual 10 CFR 50.46 Report for Calendar Year 2018 Emergency Core Cooling System Evaluation Changes

Annual 10 CFR 50.46 Report for Calendar Year 2018 Emergency Core Cooling System Evaluation Changes

ML19155A057
Person / Time
Site:	Arkansas Nuclear   (DPR-051, NPF-006)
Issue date:	06/04/2019
From:	Arnold T Entergy Operations
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
0CAN061901
Download: ML19155A057 (5)

Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-7826 Timothy L. Arnold Manager, Regulatory Assurance Arkansas Nuclear One 10 CFR 50.46 0CAN061901 June 4, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

Annual 10 CFR 50.46 Report for Calendar Year 2018 Emergency Core Cooling System Evaluation Changes Arkansas Nuclear One, Units 1 and 2 NRC Docket Nos. 50-313, 50-368, and 72-13 Renewed Facility Operating License Nos. DPR-51 and NPF-6

Reference:

Entergy Operations, Inc. letter to U. S. Nuclear Regulatory Commission, Commission (NRC), "Annual 10 CFR 50.46 Report for Calendar year 2017 Emergency Core Cooling System Evaluation Changes," dated June 5, 2018 (ADAMS Accession No. ML18156A313)

Dear Sir or Madam:

10 CFR 50.46(a)(3)(ii) requires licensees to report annually each change to, or error discovered in an acceptable evaluation model, or in the application of such model for the emergency core cooling system (ECCS) that affects the peak cladding temperature (PCT). Entergy Operations, Inc. (Entergy), has reviewed the small and large break loss-of-coolant accident (LOCA) PCT evaluations for Arkansas Nuclear One, Units 1 and 2 (ANO-1 and ANO-2).

No issues were identified for ANO-1 or ANO-2 in 2018 that impacted the results reported for the calendar year 2017 referenced above.

A summary / overview of the information required to be submitted each year is attached to this submittal.

This submittal fulfills the reporting requirements referenced above.

0CAN061901 Page 2 of 2 This letter contains no new regulatory commitments.

If you have any questions concerning this submittal, please contact Mr. Timothy Arnold at 479-858-7826.

Sincerely, ORIGINAL SIGNED BY TIMOTHY L. ARNOLD TLA/rwc

Enclosure:

Summary / Overview of Information for Arkansas Nuclear One, Units 1 and 2 10 CFR 50.46 Annual Report for 2018 cc: Mr. Scott A. Morris Regional Administrator U. S. Nuclear Regulatory Commission Region-IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P. O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Thomas Wengert MS O-08B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852

Enclosure 0CAN061901 Summary / Overview of Information for Arkansas Nuclear One, Units 1 and 2 10 CFR 50.46 Annual Report for 2018

0CAN061901 Enclosure Page 1 of 2 Summary / Overview of Information for Arkansas Nuclear One, Units 1 and 2 10 CFR 50.46 Annual Report for 2018 Analysis of Record (AOR)

Peak Clad Temperature Adjustment as New (PCT), (°F) of End-of-Year Net PCT at the Adjustments for Net PCT at the (EOY) 2017, EOY 2017, (°F) Calendar Year EOY 2018, (°F)

Evaluation Model (EM) Used

(°F) 2018, (°F)

AOR Date ANO-1 Small-Break 1459 Loss-of-Coolant 1459 1459 RELAP5 / MOD2-B&W None None Accident (estimated) (estimated)

(SBLOCA) February 2011 Large-Break 2008.1 Loss-of-Coolant 2008.1 2008.1 RELAP5 / MOD2-B&W None None Accident (estimated) (estimated)

(LBLOCA) July 2005 (Note 1)

ANO-2 2111 2111 2111 SBLOCA S2M None None (analyzed) (analyzed)

October 2007 2144 2144 2144 LBLOCA 1999 EM None None (analyzed) (analyzed)

January 2008

0CAN061901 Enclosure Page 2 of 2 Notes:

1. Framatome has completed a new ANO-1 LBLOCA analysis in accordance with NRC-approved methodology to address thermal conductivity degradation(1,2). The analysis was completed in September 2018(3) and formally transmitted to ANO in January 2019(4),

and it entered ANO-1s design and licensing basis in February 2019. The results of this analysis depict a 17º F reduction in PCT, leaving 1991º F (analyzed)(5). Due to the timing, these results are not captured in the above table and will appear in next 10 CFR 50.46 Annual Report for ANO.

References:

1. Framatome Topical Report BAW-10192PA-00, "BWNT LOCA - BWNT Loss-of-Coolant Accident Evaluation Model for Once-Through Steam Generator Plants."

2. Framatome Topical Report BAW-10192PA-00_Supplement_1PA-000, "BWNT LOCA - BWNT Loss-of-Coolant Accident Evaluation Model for Once-Through Steam Generator Plants."

3. Framatome Document FS1-0039424, Revision 1.0, "ANO-1 LBLOCA Summary Report", September 2018.

4. Framatome Letter FS1-0041794, Revision 1.0, "Transmittal of Framatome Fuel Thermal Conductivity Degradation LBLOCA Analyses for Potential PCT Reporting under 10 CFR 50.46", dated January 16, 2019.

5. Framatome Letter FS1-0043205-1.0, "Transmittal of Input for ANO-1 50.46 Report for 2018", dated March 26, 2019.