ML20214R922

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Forwards EGG-NTA-7634, Technical Evaluation Rept,Tmi Action NUREG-0737 (II.D.1) Relief & Safety Valve Testing,Fort Calhoun, Informal Rept
ML20214R922
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/23/1987
From: Roberts E
EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To: Carrington M
Office of Nuclear Reactor Regulation
Shared Package
ML20214R923 List:
References
CON-FIN-A-6492, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM EWR-58-87, NUDOCS 8706090056
Download: ML20214R922 (1)


Text

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l Mr. M. Carrington, Program Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1

TRANSMITTAL OF TECHNICAL EVALUATION REPORT, "TMI ACTION--NUREG-0737 (II.D.1) RELIEF AND SAFETY VALVE TESTING, FORT CALHOUN,"

DOCKET NO. 50-285, EGG-NTA-7634, March 1987 - EWR-58-87 Ref: INEL Technical Assistance To The Office of Nuclear Reactor Regulation, " Evaluation of OR Licensing Actions - NUREG 0737, II.D.1" (FIN A6492)

Dear Mr. Carrington:

In accordance with the above reference, INEL has been providing technical assistance to the Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation for the evaluation of plant-specific licensing submittals regarding qualification of safety and relief valves.

The enclosed report is an evaluation of the Fort Calhoun (Docket No. 50-285) submittal. This evaluation found that the licensee, Omaho ou blic Power District, has not providad acceptable submittals and responses to requests for additional information to reconfirm that the General Design Criteria 14, 15, and 30 of Appendix A to 10 CFR 50 have been met.

Very truly yours, I E. Wayne Roberts, Manager NRC Headquarters Support l CLN,cIn

Enclosure:

As Stated cc: P. T. Kuo, NRR-PBEB G. L. Jones, DOE-ID C. G. Hammer, NRR-PBEB J. O. Zane, EG&G Idaho (w/o Encl.)

[EGsGu,,.. 1142s Rockvitte pike sufre 410 nockvine, MD 20asz 8706090056 870323 PUR ADOCK 05000285

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