Letter Regarding Cancellation of Licensee Event Report
Person / Time
ML072980695
Site:	River Bend
Issue date:	10/16/2007
From:	Lorfing D Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
G9.5, RBF1-07-0190, RBG-46273 LER 07-001-00
Download: ML072980695 (2)
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LER-2007-001, Letter Regarding Cancellation of Licensee Event Report

Event date:
Report date:
4582007001R00 - NRC Website
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text

Entergy Operations, Inc.

River Bend Station 5485 J.S. Highway 61 N St. Francisville, LA 70775 Tel 225 381 4157 Fax 2 25 635 5068 dlorfingentergy.com David N. Lorfing Manager-Licensing October 16, 2007 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Cancellation of Licensee Event Report River Bend Station - Unit 1 Docket No. 50-458 License No. NPF-47 File No.

G9.5 RBG-46273 RBF1-07-0190

Dear Sir or Madam:

On March 8, 2007, River Bend Station (RBS) submitted Licensee Event [Report (LER) 50-458 / 07-001-00. The reported condition involved the loss of a traversing incore probe (TIP), an item inventoried by the station as special nuclear material (SNM). The LER was submitted in accordance with 1 OCFR20.2201 (a)(1)(ii) as a loss of licensed material of a quantity greater than ten times the quantity specified in Appendix C of that part.

As described in the LER, an inventory of non-fuel SNM materials on February 6, 2007, failed to locate the probe in its expected location. The initial investigation of this condition concluded that the TIP had likely been shipped to the licensed disposal facility at Barnwell, SC. However, during an annual inventory conducted on September 25, 2007, the TIP detector was found in the SNM storage room in the radioactive waste building inside the plant. The detector had been separated from its drive cable, and was in the bottom of a 55-gallon drum under a layer of moisture absorbent material.

The TIP probe had never been put into service, and was thus unirradiated. A new TIP probe contains approximately 0.75 milligrams of uranium-235, with a total activity of approximately 0.05 microcuries. The contact dose reading on the

Cancellation of Licensee Event Report RBF1-07-0190 October 16, 2007 Page 2 of 2 probe is less than 0.5 millirem per hour. Thus, this condition did not present an opportunity for excessive dose to radiation workers.

In accordance with the guidance of NUREG-1022, Event Reporting Guidelines, this letter is being submitted to cancel the subject LER. The TIP probe was never removed from the SNM storage area in the plant.

If you have any questions concerning this request, please contact me at 225-381-4157.

Sincerely, David N. Lorfing Manager - Licensing DNL/DHW cc:

U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Sr. Resident Inspector P. 0. Box 1050 St. Francisville, LA 70775 INPO Records Center E-Mail Mr. Jim Calloway Public Utility Commission of Texas 1701 N. Congress Ave.

Austin, TX 78711-3326 Mr. Jeff Meyers Louisiana Department of Environmental Quality Office of Environmental Compliance P.O. Box 4312 Baton Rouge, LA 70821-4312

Licensee Event Report

River Bend

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		Reporting criterion
05000458/LER-2007-001, Letter Regarding Cancellation of Licensee Event Report	Letter Regarding Cancellation of Licensee Event Report
05000458/LER-2007-002, Regarding Unplanned Manual Reactor Scram Due to Loss of Cooling on No. 2 Main Transformer	Regarding Unplanned Manual Reactor Scram Due to Loss of Cooling on No. 2 Main Transformer	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(B)
05000458/LER-2007-003, Re Unanalyzed Condition of Emergency Diesel Generator in Post-Fire Safe Shutdown Scenario	Re Unanalyzed Condition of Emergency Diesel Generator in Post-Fire Safe Shutdown Scenario	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000458/LER-2007-004, Regarding Emergency Diesel Generator Failed Surveillance Test Due to Paint on Fuel Injector Control Linkage	Regarding Emergency Diesel Generator Failed Surveillance Test Due to Paint on Fuel Injector Control Linkage	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000458/LER-2007-005, Unplanned Reactor Scram During Surveillance Testing Due to Damaged Terminal Board	Unplanned Reactor Scram During Surveillance Testing Due to Damaged Terminal Board	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000458/LER-2007-006, Regarding Unplanned Reactor Scram Due to Transformer Fault	Regarding Unplanned Reactor Scram Due to Transformer Fault	10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ix)(A), Prevented Safety Function in Multiple System 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

05000458/LER-2007-001, Letter Regarding Cancellation of Licensee Event Report

text

Subject:

Dear Sir or Madam:

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