ML20107M665
| ML20107M665 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, 05000000 |
| Issue date: | 02/22/1985 |
| From: | Tramm T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 9776N, NUDOCS 8503010384 | |
| Download: ML20107M665 (2) | |
Text
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Commonwealth Edison ont First Nation 31 Platt. ChicTgo. Ilknois Address Reply to: Post Office Box 767 Chicago. Illinois 60690 February 22, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Fashington, DC 20555
Subject:
Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 Instrumentation for the Detection of Inadequate Core Cooling NRC Docket Nos. 50-454/455 and 50-456/457 Reference (a):
September 25, 1984 letter from T. R.
Tramm to H. R. Denton.
Dear Mr. Denton:
This letter provides a report on the implementation of the Byron /Braidwood instrumentation for the detection of inadequate core cooling (ICC).
This Implementation Letter Report is supplied at the request of the NRC staff per section 4.4 of Supplement 5 to the Byron Safety Evaluation Report.
Installation of the Byron 1 ICC instrumentation was completed in November of 1984.
The system was tested and the results approved by November 22, 1984.
Test Procedure CX-2.20-21, Component Demonstration C-219, verified that the proper information was displayed on the Safety Parameter Display System (SPDS) for subcooling margin.
The test results are available for review.
Final debugging of the SPDS iconic display is in progress but the digital display of subcooling will usually be available to the operator either on the iconic display or another CRT screen.
The ICC System performs in accordance with design expecta-tions.
The objectives and all expected values were satisfied.
As of Amendment 46, FSAR Appendix E, Section E.31, adequately describes the instrumentation used to detect inadequate core cooling.
Section 3/4.3.3.6 and Table 3.3-10 of the Byron Technical Specifications already contain operability requirements for the ICC instrumentation.
No Tech Spec changes are being proposed at this time.
8503010384 850222 PDR ADOCK 05000454 h4 E
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F H. R. Denton February 22, 1985
-The Byron Station Emergency Operating Procedures (EOP) will conform to the NRC approved Westinghouse Owners Group (WOG) Emergency Procedure Guidelines (EPG), Revision 1.
The WOG EPG's were approved by the NRC on December 27, 1984.
To satisfy a condition of the Byron-Operating License, the E0P's will be submitted to the NRC on or'about March 1, 1985.
The revised procedures are expected to be implemented by August 1, 1985.
Please address further questions regarding this matter to this office.
Very truly yours,
[1 0s W T. R. Tramm Nuclear Licensing Administrator 1m cc:
Byron Resident Inspector 9776N
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