ML19257C659
| ML19257C659 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/18/1980 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| TLL-028, TLL-28, NUDOCS 8001290560 | |
| Download: ML19257C659 (3) | |
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Metropolitan Edison Company g
Post Office Box 480 Middletown, Pennsylvania 17057 717 944-4041 Writer's Direct Dial Number January 18, 1980 TLL 028 Director of Nuclear Reactor Regulation Attn:
R. W. Reid, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License t'o. DPR-50 Docket No. 504289 TMI-I PORV v t.,ation In our letter GOL 1439 dated November 27, 1979, we inadvertently reported that reactor trip number 12 was not a result of high RCS pressure. We have now confirmed that this trip was caused by high RC pressure. The response to your September 28, 1979 request has been revised to reflect this change.
Revised page one of that response is attached. There are no changes to page 2.
Sincerely, 191A R. C.
rnold Senior Vice President RCA:CFM: hah Attachment 1827 219 9
9
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s Metroco'. tan Ec son Company s a Memcer of :ne Ger al Put?c UtSt es System 3001290
s Enclosure to TLL 028 TMI-I PORV Actuation Revised Request No. 1 According to statements made by B&W, there are approximately 146 documented occasions where PORV actuation occurred at B&W facilities prior to the accident at Three Mile Island, Unit II (TMI-2). For each of these events which have occurred at your facility (ies), provide the following information:
a.
The cause of the event; b.
The initial power level prior to the transient; c.
Indicate which of these transients caused the reactor to trip on high RCS pressure and/or caused the safety valves to lift; and, d.
If you assume that the present setpoints for high RCS pressure trip and PORV actuation were in effect at the time of each of these transients, estimate whether either of the following would have taken place;
- 1) PORV actuation, and 2) lifting of the safety valves.
Response
The following matrix provides information for parts a., b., and c., above:
Power Reactor Trip Code Safety Cause of Level on High RCS Valve Event /Date Event Pressure Actuate Reactor Trip #1/
Partial loss of 6/18/74 instrument air 7
No No Reactor Trip #6/
Electrical problems 7/12/74 with turbine 65 No No Reactor Trip #7/
Loss of Feedwater 15 No No 7/13/74 Reactor Trip #8/
Inadvertent grounding 7/14/74 of RCS Tave signal 76 No No Reactor Trip #10/
Manual turbine trip 8/13/74 for TP 800/34 98 Yes No Turbine Trip /
Turbine bearing 8/30/74 Failure 75 No No Turbine Trip /
High moisture separator 100 No No 1/23/75 drain tank level Reactor Trip #12/
Laas of 125 VDC power 3/30/75 to EHC 100 Yes No 1829 220
Enclosure to TLL 028 TMI-I PORV Actuation Revised page 2 Reactor Trip #13/
High moisture 100 Yes No 5/09/75 separator level Reactor Trip #14/
Voltage spikes in 100 Yes No 6/18/75 turbine EHC system caused load transient 1829 221