GNRO-2011/00102, Report of Changes and Errors to 10 CFR 50.46
| ML113340042 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/29/2011 |
| From: | Perino C Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| GNRO-2011/00102 | |
| Download: ML113340042 (2) | |
Text
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- ~Entergy GNRO-2011/00102 November 29, 2011 Entergy Operations, Inc.
PO Box 756 Port Gibson, Mississippi 39150 Tel: 601-437*2800 Christina L Perino Licensing Manager U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
Report of Changes and Errors to 10CFR50.46 Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29
REFERENCES:
1.
Letter GNRO-2010/00069, "Report of Changes and Errors to 10CFR50.46," dated November 15, 2010.
2.
Letter GNRI-2008-00083, "GRAND GULF NUCLEAR STATION, UNIT 1 - ISSUANCE OF AMENDMENT RE: CHANGES TO TECHNICAL SPECIFICATION 5.6.5, CORE OPERATING LIMITS REPORT (TAC NO. MD7493)," dated October 16, 2008.
Dear Sir or Madam:
In accordance with 10CFR50.46 (a)(3)(ii), Grand Gulf Nuclear Station, Unit 1 (GGNS) is required to report to the Commission, at least annually, the estimated effect on the limiting Emergency Core Cooling System (ECCS) analysis caused by changes to or errors discovered in acceptable ECCS evaluations for information.
Since the last 10CFR50.46 report dated November 15, 2010 [see reference 1], two notices of changes or errors associated with the current GGNS ECCS analysis have been identified. The table below summarizes these changes or errors and the effect on the current ECCS analysis performed by General Electric-Hitachi Nuclear Energy (GEH) using their NRC approved SAFER/GESTR-LOCA methodology.
GNRQ-2iUJlQQJ 02 Page 2 of 2 Estimated PCT Effect Notification Nature of Change (l1PCT)
AT10 GE14 GNF2 NL-2011-02 Impact of database error for heat deposition
+15
+15
+15 on the Peak Cladding Temperature (PCT) for 1Ox1 0 fuel bundles.
NL-2011-02 Impact of updated formulation for gamma
+20
+20
+20 heat deposition to channel wall for 9x9 and 1Ox1 0 fuel bundles.
Sum of absolute magnitude of errors during this period
+35
+35
+35 Cumulative sum of absolute magnitude of errors prior to 0
0 0
this period Cumulative sum of absolute magnitude of errors including
+35
+35
+35 this period The overall impact to the GGNS licensing basis PCT as a result of the errors and changes listed above is an increase of 35°F. As such, the licensing basis PCT of the limiting ATRI UM-1 0 (AT10) fuel type reported in reference 2 increased from <1880 OF to
<1915 OF, which remains well below the 2200°F acceptance criterion of 10CFR50.46.
This letter does not contain any commitments. Should you have any questions or require additional information, please contact Cassandre Justiss at 601-437-6685.
Sincerely, CLP/CJ cc:
Mr. Elmo E. Collins, Jr.
Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 612 East Lamar Blvd., Suite 400 Arlington, TX 76011-4125 U. S. Nuclear Regulatory Commission ATTN: Mr. A. Wang, NRR/DORL Mail Stop OWFN/8 G14 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150