0CAN061901, 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 (PCT), (°F)
Evaluation Model (EM) Used AOR Date Adjustment as of End-of-Year (EOY) 2017,
(°F)
Net PCT at the EOY 2017, (°F)
New Adjustments for Calendar Year 2018, (°F)
Net PCT at the EOY 2018, (°F)
ANO-1 Small-Break Loss-of-Coolant Accident (SBLOCA) 1459 RELAP5 / MOD2-B&W February 2011 None 1459 (estimated)
None 1459 (estimated)
Large-Break Loss-of-Coolant Accident (LBLOCA) 2008.1 RELAP5 / MOD2-B&W July 2005 (Note 1)
None 2008.1 (estimated)
None 2008.1 (estimated)
ANO-2 SBLOCA 2111 S2M October 2007 None 2111 (analyzed)
None 2111 (analyzed)
LBLOCA 2144 1999 EM January 2008 None 2144 (analyzed)
None 2144 (analyzed)
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."
- 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.