ML20101A104
| ML20101A104 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/13/1984 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 5211-84-2295, GL-83-28, NUDOCS 8412180126 | |
| Download: ML20101A104 (2) | |
Text
e g
GPU Nuclear Corporstloc Nuclear
- ,omear8o Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
Decerrber 13, 1984 5211-84-2295 Office of Nuclear Reactor Regulation Attn:
D. G. Eisenhut, Director
-Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Required Actions Based on Generic Implications of Salem /ATWS Events
Reference:
(1) GPUN Letter, H. D. Hukill to D. G. Eisenhut dated November 8,1983 (2) B&W Owners Group ATWS Committee Response to Generic Letter 83-28, dated November 4,1983 item 4.4 Reference 1 forwarded the GPU Nuclear Corporation response to Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem /ATWS Events."
Item 4.4 of Generic Letter 83-28 requires that licensees with B&W reactors apply safety related maintenance and test procedures to the diverse reactor trip feature provided by interrupting power to control rods through the silicon controlled rectifiers. Enclosed is a correction to Reference 1, identifying the maintenance and test procedures applied to the diverse trip as Important to Safety. The change is indicated by margin bar. Consistent with the B&W Owners Group Position (Reference 2), the electronic trip and SCR's do not have a safety classification.
Sincerely, 8412180126 841213 I
PDR ADOCK 05000289 P
PDR I. D.1 ill Director - TMI-1 I
SK: dis:0878f pd Enclosure 8
t i
GPU Nuciear Corporation is a subsidiary of the General Public Utilities Corporation
,g
_4.4 Reactor Trip System Reliability Procedures for testing and maintenance of the diverse reactor trip feature are classified as Important to Safety (see item 2.1). The trip feature includes the electronic trip and SCRs.
The trip function of the SCRs was not previously verified. A change to test procedure 1303-4.1 (Reactor Protection System) has been approved and was distributed. The revised procedure confirms the trip function by verifying the reduction in current from the affected power supply.
The language of the TMI-1 Tech Specs is broad enough to cover the SCR portion of the trip function. However, for clarity, an administrative Tech Spec change will be included with several other administrative changes at a future convenient time.