IR 05000320/1978039
| ML19224A549 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/10/1979 |
| From: | Bettenhausen L, Caphton D, Mcnatt T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19224A548 | List: |
| References | |
| TASK-TF, TASK-TMR 50-320-78-39, NUDOCS 7903080096 | |
| Download: ML19224A549 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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Region I Report No. 50-320/78-39 Docket No. 50-320 License No. DPR-73 Priority
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Category _ C Licensee: Metropolitan Edisor Company P. O. Box 542 Reading, Pennsylvania Facility Name:
Three Mile Island Nuclear Station, Unit 2 Inspection at:
Middletown, Pennsylvania Inspection conducted:
December 28-29, 1978
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i In5Dectors:
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H. Beitt'enhausen, Reactor Inspector date signed h>
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T. G. McNit't, Reactor' Inspector
' date signed Approved by:
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D. L. Caphto#n, Chief, Nuclear Support
' date signed Section #1, RO&NS Branch Insoection Summary:
Inspection on December 28-29, 1978 (Recort No. 50-320/78-39)
Area Inspected:
Routine, unannounced inspection by 2 regional based inspectors of transient test (witness) - generator trip fron 96% power and preliminary review of test data.
The inspection involved 12 inspector hours on site by 2 NRC regional based inspectors.
Results:
No items ci noncompliance were identified.
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u s.J -7d8 Region I Forn 12 (Rev. April 77)
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DETAILS 1.
Persons Contacted Metrocolitan Ed.ison Comoany Mr. J. Chwastyk, Shift Supervisor Mr. J. Floyd, Unit 2 Supervisor of Operations Mr. G. Knuder, Unit 2 Superintendent - Technical Support Mr. J. Logan, Unit 2 Superintendent General Public Utilities Service Corocration
- Mr J. Garrison, Test Engineer
- Mr. T. Hawkins, Assistant Test Sucerintendent Babcock and Wilcox Mr. J. Flint, Startup Test Engineer Mr. J. Putnam, Startup Engineer The inspectors also interviewed other licensee personnel, including control room operators, technical and instrumentation staff personnel, during this inspection.
- denotes those present at exit interview on December 29, 1978.
2.
Witness of Generator Trio Test from 96% Power Inspectors were onsite to witness the conduct, on December 28, 1978, at 11:18 p.m., of Startup Procedure T? SCO/3a, " Generator Trip Test", Revision 0, for the purpose of verifying conformance to license and procedural requirements, observing operating staff performance, and re. ?cwing the preliminary test results evaluation.
a.
Control Room Observations One inspector witnessed tne test from the Control Room to observe test / operating crew performance and system response.
The two 500 KV generator output breakers were opened from the control console at 11:18: 30 p.m. on December 28, 1978.
The generator trip was followed by a turbine overspeed trip and a runback in reactor power to 15%.
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The inspector in the Control Room verified:
(1)
The current procedure was available and in use by oil crew members.
(2)
The Control Room was manned in accordance with the Tech-nical Specifications.
(3)
Sufficient test personnel were available to assure the orderly recording and evaluation of test data.
(4)
Test prerequisites were met.
(5)
The plant was initially operating between 95% and 100%
power.
(6)
The test was performed as required by the procedure.
(7)
Crew actions appeared to be correct, timely, and ade-quately coordinated.
(8) A quick summary analysis was made by the licensee to assure proper plant response.
(9)
Data was collected for final analysis by the licensee.
b.
Observations at Startuo Pa'.ch Panel The inspector at the Startup Patch Panel verified:
(1)
Special test equipment was calibrated and operationai.
(2)
The test was performed as required by the procedure.
(3) Crew actions were coordinated.
(4)
The current procedure was available and in use by crew members.
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c.
Preliminary Evaluation of Test Results Direct observation by the inspector and preliminary review of process computer and strip chart data recordings by the inspector and the licensee indicated that Technical Specifications were met and that test acceptance criteria, except as noted below, were satisfied.
The following test parameters could not be ascertained to meet ac.ceptance criteria on the Lasis of preliminary raw data:
RCS pressure at wnich pressurizer spray valve opens and
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closes.
RCS pressure at which pressurizer electromatic relief
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valve opens and closes.
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Reactor power run back rate.
Main steam safety valve lift pressures.
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Review of detailed data for these carameters will be accomplished during a subsequent inspection (320/78-39-01).
No items of noncompliance were identified.
3.
Exit Interview An exit interview was held at the conclusion of the inspection with test personnel identified in Paragraph 1.
The parameters identified in Paragraph 2.c were discussed at' this meeting.
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