ML19322D223
| ML19322D223 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/21/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Deyoung R NRC - NRC THREE MILE ISLAND TASK FORCE |
| Shared Package | |
| ML19322D224 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8002100067 | |
| Download: ML19322D223 (1) | |
Text
S;nt Facsimile to R. C. DaYoung, 6/21/79 l
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MEMORANDUM FOR:
R. C. DeYoung, Interim Deputy Director NRC/TMI Special Inquiry Group FROM:
B. H. Grier, Director, Region I
SUBJECT:
INFORMATION ON REACTOR TRIP (F01000939)
In response to your memorandum dated June 14, 1979 on this subject, we reviewed our inspection records and docket file for Three Mile Island Ur.it 2 but found no report or other evidence of a reactor trip having occurred on April 19, 1978.
Subsequently, a review of licensee records was performed at Three Mile Island by Don Haverkamp, Region I Reactor Inspector.
This review included the Control Room Operator's Log Book, the Shift Foreman's Log Book and the Nuclear Engineer's file of Reactor Trip Reports. All of the aforementioned records indicate that a reactor trip did occur on April 19, 1978 at 0601 hours0.00696 days <br />0.167 hours <br />9.937169e-4 weeks <br />2.286805e-4 months <br /> but do not place any significance on the event probably because the trip occurred from only 15% power. The Reactor Trip Report (No. 2, dated 4/19/78, copy attached) intimates that operator error may have been the cause by the wording used in Item 5 - Corrective action to pre-vent occurrence.
It should be noted that the event was not reportable to NRC under the facility's T.S.'s and, therefore, no Licensee Event Report was submitted nor was the trip included in the licensee's Monthly Operating Report.
Licensee records show the reactor was critical at approximately 15% power in prep-aration for a turbine roll.
Operators were blowing down suction strainers in the condensate system.
The condensate pumps tripped on low suction pressure which led to a trip of the main feedwater pumps.
This caused high reactor pressure and re-sulted in a reactor trip at 0601.
The reactor was returned to criticality at 1355 on April 19, 1978.
We trust that this information meets your needs.
Region I plans to take no addi-tional action with regard to this matter.
B H. Grier Director cc:
W. Parler W. Lanni.ng
Enclosure:
TMI Reactor Trip Report #2 l
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