GNRO-2015/00020, Revision to Letter GNRO-2014/00091 Dated January 6,2015 to Add Revision Number Eight (8) to Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density

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Revision to Letter GNRO-2014/00091 Dated January 6,2015 to Add Revision Number Eight (8) to Reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density
ML15089A126
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 03/27/2015
From: Kevin Mulligan
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2015/00020
Download: ML15089A126 (4)
v • d • e


Text

~Entergy Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150 Kevin MUlligan Site Vice President Tel. (601) 437-7500 GNRO-2015/00020 March 27,2015 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

SUBJECT:

Revision to letter GNRO-2014/00091 dated January 6,2015 to add revision number eight (8) to reference NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1. Letter: Revision to Technical Specification 5.6.5.b to add reference to NEDC-33075P-A, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density, dated January 6, 2015 (GNRO-2014/00091 )
2. Letter: Grand Gulf Nuclear Station Unit 1, Maximum Extended Load Line Limit Analysis Plus (MELLLA+) License Amendment Request dated September 25, 2013 (GNRO-2013/00012, NRC ADAMS Accession No. ML3269A140)

Dear Sir or Madam:

Entergy Operations Inc. (Entergy) proposes to revise reference 1 letter to add the words "Revision 8" to the added reference proposed for TS 5.6.5.b as follows: NEDC-33075P-A, Revision 8, GE Hitachi Boiling Water Reactor Detect and Suppress Solution - Confirmation Density (DSS-CD). This will ensure that the approved DSS-CD methodology can be used for preparing the Cycle Operating Limits Report (COLR) for the MELLLA+ reload following the approval of the MELLLA+ License Amendment Request.

This reference will be added upon NRC approval.

This letter contains no new commitments. If you have any questions or require additional information, please contact James Nadeau at 601-437-2103.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 27th day of March, 2015.

GNRO-2015/00020 Page 2 of 2 Sincerely,

~~/ r ---'- _

2

~-----

KJM/ras

Attachment:

1) Technical Specification Page 5.0-21 Clean cc:

U.S. Nuclear Regulatory Commission ATTN: Mr. A. Wang, NRRlDORL Mail Stop OWFN/8 G14 11555 Rockville Pike Rockville, MD 20852-2378 NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U. S. Nuclear Regulatory Commission ATTN: Marc L. Dapas (w/2)

Regional Administrator, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511

Attachment to GNRO-2015/00020 Technical Specification Page 5.0-21 Clean

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 Core Operating Limits Report (COLR) (continued)

21. NEDE-33383-P, "GEXL97 Correlation Applicable to ATRIUM-10 Fuel," Global Nuclear Fuel.
22. EMF-CC-074 (P) (A), Volume 4, "BWR Stability Analysis Assessment of STAIF with Input from MICROBURN-B2",

Siemens Power Corporation, Richland, WA.

23. EMF-2292 (P) (A), "ATRIUM-10 Appendix K Spray Heat Transfer Coefficients", Siemens Power Corporation, Richland, WA.
24. NEDE-240ll -P-A, General Electric Standard Application for Reactor Fuel (GESTAR-II).
25. NEDO-3l960-A, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology"
26. NEDO-32465-A, "Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications"
27. NEDC-33075P-A, Revision 8, "GE Hitachi Boiling Water Reactor Detection and Suppress Solution - Confirmation Density."
c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

GRAND GULF 5.0-21 Amendment No. +/-+3, ~ 188,

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