HNP-14-062, Annual Report of Changes Pursuant to 10 CFR 50.46
| ML14139A137 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 05/19/2014 |
| From: | Brewer H Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| HNP-14-062 | |
| Download: ML14139A137 (4) | |
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May 19,
Serial: HNP-14-062 ATTN: Document Control Desk 86Nuclear Regulatory Commission Washington, DC
Shearon Harris Nuclear Power Plant, Unit 1 Docket No.
Subject:
Annual Report of Changes Pursuant to CFR
Ladies and Gentlemen:
H. Duncan Brewer Director, 2UJDQL]DWLRQDOEffectiveness Harris 1XFOHDU3ODQW 5413 6KHDURQHarris Road New +LOO 1&
919.362.2305
CFR
Pursuant to CFR 50.46(a)(3)(ii), Duke Energy Progress,,QFhereby submits the enclosed annual report of changes to and errors discovered in the loss of coolant accident analyses for the Shearon Harris Nuclear Power Plant, Unit 1, for the period April 24, through April 9,
This document contains no regulatory commitments. Please refer any questions regarding this submittal to John Caves at (919) 362-2406.
Sincerely, H. Duncan Brewer HDB/jrc
Enclosure:
Annual Report of Changes Pursuant to CFR
cc:
Mr. J. D. Austin, NRC 6U Resident,QVSHFWRUHNP Ms. M. Barillas, NRC Project Manager, HNP Mr. 9M. McCree, NRC Regional Administrator, Region,,
H. Duncan Brewer Director, Organizational Effectiveness Harris Nuclear Plant 5413 Shearon Harris Road New Hill NC 27562-9300 919.362.2305 May 19, 2014 Serial: HNP-14-062 10 CFR 50.46 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400
Subject:
Annual Report of Changes Pursuant to 10 CFR 50.46 Ladies and Gentlemen:
Pursuant to 10 CFR 50.46(a)(3)(ii), Duke Energy Progress, Inc. hereby submits the enclosed annual report of changes to and errors discovered in the loss of coolant accident analyses for the Shearon Harris Nuclear Power Plant, Unit 1, for the period April 24, 2013, through April 9, 2014.
This document contains no regulatory commitments. Please refer any questions regarding this submittal to John Caves at (919) 362-2406.
Sincerely, H. Duncan Brewer HDB/jrc
Enclosure:
Annual Report of Changes Pursuant to 10 CFR 50.46 cc:
Mr. J. D. Austin, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP Mr. V. M. McCree, NRC Regional Administrator, Region II
U.S. Nuclear Regulatory Commission Page 1 of 2 Enclosure to HNP-14-062 Shearon Harris Nuclear Power Plant, Unit 1 Annual Report of Changes Pursuant to 10 CFR 50.46 Reporting Period April 24, 2013 through April 9, 2014 Small Break Loss of Coolant Accident (SBLOCA) Analysis The SBLOCA analysis is impacted by a reanalysis and one error discovered during this reporting period.
SBLOCA PCT Summary of Changes PCT
(°F)
Resultant PCT (°F)
Previously reported SBLOCA PCT effective April 23, 2013 1631 Changes during reporting period New Analysis of Record Error: Implementation of a vapor absorptivity correlation
+33
+17 1664 1681 SBLOCA PCT effective April 9, 2014 1681 The resultant predicted fuel element PCT, accounting for changes and errors in the evaluation model, is within the 2200 °F acceptance criteria in 10 CFR 50.46(b)(1).
U.S. Nuclear Regulatory Commission Page 2 of 2 Enclosure to HNP-14-062 Large Break Loss of Coolant Accident (LBLOCA) Analysis The LBLOCA analysis is impacted by a reanalysis and two errors discovered during this reporting period.
LBLOCA PCT Summary of Changes PCT
(°F)
Resultant PCT (°F)
Previously reported LBLOCA PCT effective April 23, 2013 2071 Changes during reporting period Error: RODEX3a incorrectly modeled trapped stacks New Analysis of Record Includes conservative adder to account for uncertainties related to droplet shattering and fuel relocation of
+138 °F as required by the NRC safety evaluation documenting approval of ANP-3011 Incorporates the RODEX3a error described above Error: Implementation of a vapor absorptivity correlation
-10
+12 0
2061 2073 2073 LBLOCA PCT effective April 9, 2014 2073 The resultant predicted fuel element PCT, accounting for changes and errors in the evaluation model, is within the 2200 °F acceptance criteria in 10 CFR 50.46(b)(1).