ML20214R922
| ML20214R922 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| 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
[OA
=
/NEA ikho National Engineerksg Laboretory yaych 23, }gg]
l Mr. M. Carrington, Program Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 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 o blic Power District, has not providad acceptable licensee, Omaho u
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, E. Wayne Roberts, Manager NRC Headquarters Support 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
.