ML20207S071
| ML20207S071 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/13/1987 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 5211-87-2062, NUDOCS 8703180490 | |
| Download: ML20207S071 (2) | |
Text
.
GPU Nuclear Corporation NQQIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 o191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
March 13, 1987 5211-87-2062 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Correction to GPUN Letter of March 9,1987 -
5211-87-2051 On March 9,1987, GPUN submitted a letter entitled " Safety Parameter Display System Isolation Device Test Results" (letter no. 5211-87-2051). This letter was submitted without the operating license nunber and docket number for THI-1.
Attached is a corrected copy of page 1 of the cover letter. Please replace the existing page with the attached page. The remaining pages are correct and should be retained.
We apologize for the inconvenience.
t l
Sincerely, l
. D.
<ill Vice President & Director, THI-l HDH/SM0/spb:0823A cc:
T. E. Murley R. Conte 8703180490 870313
[9 PDR ADOCK 05000289 P
PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation i
GPU Nuclear Corporation NggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944-7621 TELEX 84-2386 Writer's Direct Dial Nurnber:
March 9' 1987 5211-87-2051 U.S. Huclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Three Mile Island Nuclear Generating Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Safety Parameter Display System Isolation Device Test Results In the NRC Safety Evaluation Report on the THI-l Safety Parameter Display System (Reference 1), the NRC identified an open item with respect to a test program and test results for the Rochester Instruent Model SC-1302, which is used to buffer reactor coolant pump power from the computer. The test report was to demonstrate that the device is qualified to protect safety systems (i.e., PPS related pump power monitors) from maximum credible faults. The SER requested that GPUN provide the following:
1.
Test procedure showing test configuration and acceptance criteria 2.
Test results to verify that the maximum credible fault was applied to the output of the Model SC-1302 in the transverse mode (between signal and return) and no perturbations were seen on the Class lE input.
A simplified sketch of the reactor coolant pump power monitor is provided as Attachent 1.
Rochester Instruent Systems was contracted to perform the testing. The test procedure is provided as Attachment 2.
Test results are provided as Attachent 3.
TEST RESULTS Test 2Cc is the specific transverse fault requested. Tests 2Ca and 2Cb were also performed for completeness.
(Terminals 5 & 6 are the output terminals)
Test 2Ca: 120 volts with a 20 amp capability was applied to terminal 5 and chassis ground.
A 20 millivolt.2 millisecond spike was observed on the input.
Test 2Cb:
120 volts was applied to terminal 6 and chassis ground.
A 65 millivolt.67 millisecond spike was observed on the input.
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation N--- --_ --._-
_-