ML19261F266
| ML19261F266 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/31/1974 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-0027, GQL-27, NUDOCS 7910250706 | |
| Download: ML19261F266 (4) | |
Text
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[EC D IUTICN 70R PART 50 OcCKET PX L
(TD.PORARY FCF21)
CONTP0L NC: 4966 PILE:
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DATE CF DOC DATE REC'D LTR MF.F.0 RPT' UTi.2.2 Metropolitan Edison Company Reading, Pa. 19603 5-31-74 6-4-74 X
R. C. Arnold TO:
D. L.
1 signed SDIT LOCAL PDR X CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DCCKET NO:
XXX 1
50-289 DESCRIPTION:
ENCLOSURES:
Ltr reporting abnormal occurrence A0 50-289/74-4 on 5-21-74, regarding the inadequate administ-ONOT REMnyp; rative Control of Control Rod Drive Trip Test-ing Procedure......
ACKNOWTFD'1ED PLANT NAME: Three Mile Island Unit #1
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Dear Sir:
Operating License DPR-50 Decke. #50-269 In accordance with Technical Specifications for the Three Mile Island iuclear Station Unit 1, we are reporting the folleviag abnormal occurrence:
(1)
Report Nunter: A0 50-289/7h-h (2a) Report Date: May 31, 197h (2b) Occurrence Date: May 21, 197h (3)
Facility: Three Mile Island :Iuelear Generating Station, Unit 1 (h)
Identification of Occurrence:
Title:
Inadequate Administrative Centrol of Control Rod Drive Trip Testing Procedure Type:
Violatien of Technical Specifications, paragrsph 6.2.3, whica constitutes an abnormal occurrence as defined by the Technical Specifications, pararrae 1.25, in that inadequate administrative ecntrol of the red drive trip testing procedure may have threatened to cause an unsafe condition in the cperation of the plant.
(5)
Conditions Frior to Occurrence:
Hot shutdown, with na.jor plant parameters as follows:
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. Power:
Cor?: 0 Elec: 0 RC Flow:
10h x 106 #/hr. (3 RC pu=ps)
RC Pressme:
2155 psig RC Temp:
350 F PEZR Level:
120" PRZR Te=p.-
6h6 F (6)
Description of Gecurrence:
It is a requirement of Test Procedure 330/5 (TP/330/5), Centrol Rod Drive Trip Test, to measure the trip times of the fastest and slowest rods (fastest and slowest being determined by previous trip tests ).
According to previous test results, the two reds involvedvere in group 5 and group 2 rod #3 So that the TP could be acecmplished with the fastest and slowest rod in the same group (group 5 was chosen), a patch of group 2 rod #3 to group 5 rod #2 was performed.
Rod group 5 was then withdrawn to its outlimit, at which time it was necessary to transfer group 2 rod #3 to the auxiliary power supply. Shortly after transfer was performed, power "on" lights flashed on several rods, and the reactor trip was inmediately activated. Rod drive pcwer was secured at h80V buses 1G and lL.
Damage was visible to power supply transfer switches #18 and #19 and several internal wires (10 to 15) and several fuse clip holders (h ^
5).
(T)
Designatica of Apparent Cause of Cecurrence:
Personnel, in that althcugh the test could not be performed as written, they failed to initiate a temporary change notice as required by Test Instruc-tions, and continued on with the test.
(8)
Analysis of Occurrence: When the control rod drive patch was per-formed, cnly the pcVer patch was performed while the logic patch was not.
An atte=pt to transfer group 2 rod #3 to the auxiliary power supply resulted in an overcurrent condition at the group 2 rod #3 transfer switch. The overcurrent condition resulted because the group 2 rod #3 power patch and logic patch were in disagreement.
There were no perscnnel injuries as a result of the occurrence; and equipment damage was as previously described.
As the reactor was shut down greater than 1% Ak/k during.the course of the occurrence and remained su uncil repairs were effectuated, this occurrence posed no potential censequences from the standpoint of pub?ic health and safety.
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. (9)
Corrective Action:
Immediate actions were as previously described.
The Plant Operations Review Cc==ittee met pro ptly after the incident and reccmmended to the Plant Superintendent that repairs be made to damaged equipments, invclved test personnel be briefed cn the import-ance of ecnforming to the Test Instructions, and that a control rod patching procedure be initiated and approved prior to patching any rod to other than its normal pcsition.
The Station Superintendent concurred with PCRC's recctmendaticns, repairs have been made to the damaged equipments, and involved personnel have been briefed.
In addition, the Station Superinten-dent has instructed Station Management and Supervisor perscnnel to emphasize to these reporting to then the importance of perform-ing tests in accordance with the Test Instructicns.
(10) Failure Data: Damage occurred to the folleving equipment located in Diamond Power Service Co. - Transfer Cabinet 3 and h.
1.
Motor Cutput Assembly - Fuse blocks, fuse indicating lights and viring.
2.
Transfer switches and viring to a transfer switch and a relative position indicator cedule.
Sincerely,
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C. ARNOLD Vice President-Generation RCA:DNG:eg File 20.1.1/7.7.3 5.1 cc: Directorate of Regulatory Operations, Region i U. S. Atc=ic Energy Cc= mission 631 Park Avenue King of Prussia, Pennsylvania 19hC6
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