RBG-46413, Supplement to Amendment Request Re End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation (LAR 2004-15)

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Supplement to Amendment Request Re End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation (LAR 2004-15)
ML051300241
Person / Time
Site: River Bend Entergy icon.png
Issue date: 04/16/2005
From: King R
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
RBG-46413
Download: ML051300241 (5)


Text

Entergy Operations, Inc.

-- Entergy River Bend Station 5485 U. S. Highway 61 N St. Francisville, LA 70775 Fax 225 635 5068 RBG-46413 April 19, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Supplement to Amendment Request End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation (LAR 2004-15)

River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47

REFERENCES:

Letter from Paul D. Hinnenkamp to USNRC dated September 24, 2004 (LAR 2004-15)

Dear Sir or Madam:

By the letter referenced above, Entergy Operations, Inc. (Entergy) proposed a change to the River Bend Station, Unit 1 (RBS) Technical Specifications (TSs) to revise the Operating License to allow revision of reactor operational limits, as specified in the RBS Core Operating Limits Report (COLR), to compensate for the inoperability of the End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation.

On January 27, 2005, Entergy and members of your staff held a call to discuss LAR 2004-15.

As a result of the call, three questions were determined to need formal response. Entergy's response is contained in Attachment 1.

There are no technical changes proposed. The original no significant hazards consideration included in Reference 1 is not affected by any information contained in the supplemental letter. There are no new commitments contained in this letter.

If you have any questions or require additional information, please contact Bill Brice at 601-368-5076.

RBG-46413 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct. Executed on April 19, 2005.

Sincerely, Rick J. King Director, Nuclear Safety Assurance RJK/WBB Attachments:

1. Response to Request For Additional Information related to LAR 2004-15 cc: Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector P. O. Box 1050 St. Francisville, LA 70775 U.S. Nuclear Regulatory Commission Attn: Mr. Michael K. Webb MS O-7D1 Washington, DC 20555-0001 Louisiana Department of Environmental Quality Office of Environmental Compliance Attn: Mr. Ronnie Wascom Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312

Attachment 1 To RBG 46413 Response to Request for Additional Information related to LAR 2004-15 to RBG-46413 Page 1 of 2 Response to Request for Additional Information Related to LAR 2004-15 Question 1:

What is the GE11 batch size in the current Cycle 13?

Response 1:

There are 136 GE11 assemblies in the River Bend Station (RBS) Cycle 13 core

Reference:

River Bend Station, Cycle 13 Core Operating Limits Report (COLR)

EMF-3100 Revision 0, "River Bend Station Cycle 13 Reload Analysis Question 2:

Identify the approved methods for thermal limits calculations.

Response 2:

The thermal limits (Minimum Critical Power Ratio (MCPR) and Linear Heat Generation Rate (LHGR)) calculations with and without the End of Cycle-Recirculation Pump Trip (EOC-RPT) use the same Framatome-ANP analytical methods as described in RBS Technical Specification (TS) 5.6.5. Specifically, core responses to pressurization transient events such as load rejections or turbine trips are analyzed using the COTRANSA2 computer code as approved per ANF 913.

Reference:

RBS, Cycle 13 COLR, reference 11, ANF-913(P)(A) Volume 1 and Revision 1 Volume Supplements 2, 3, and 4 COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analysis, Advanced Nuclear Fuels Corporation, August 1990 EMF-3100 Revision 0, "River Bend Station Cycle 13 Reload Analysis", reference 8.1 to RBG-4641 3 Page 2 of 2 Question 3:

Confirm that feedwater heater out-of-service was analyzed for operation without EOC-RPT.

Response 3:

The thermal margins for feedwater heater out-of-service without EOC-RPT have been analyzed in the RBS Cycle 13 Reload Analysis.

Reference:

EMF-31 00 Revision 0, "River Bend Station Cycle 13 Reload Analysis"