ML19262A230
| ML19262A230 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/09/1974 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| NUDOCS 7910260569 | |
| Download: ML19262A230 (4) | |
Text
AEC DISTRIBUT!CN FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)
CONTROL NO: 12522 FILE:
FROM: Metroplitan Edison co.
DATE OF DOC D ATE R EC'D LTR TWX RPT OTHER R*fi"h,Pa 12-9-74 12-12-74 xxxxx
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ORIG CC OTHER SENT AEC PDR X7%*T Directorate of Licensing 1-signed SENT LOCAL POR CLASS UNCLASS PROPINFO INPUT NO CYS REdD DOCKET NO:
xxxxxx 1
50-259 DESCRIPTION:
ENCLOSURES:
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Dear Sir:
Docket No. 50-289 Operating License DPR-50 In accordance with the Te.-hnical Specifications for our Three Mile Island Nuclear Station, Unit 1, we are reporting the following abnormal occurrence:
(1) Report Number: A0 50-289/74-27 (2a) Report Date: December 9,1974 (2b) Occurrence Date: November 29, 1974 (3)
Facility: Three Mile Island Nuclear S tation, Unit 1 (TMI-1)
(4) Identification of Occurrence:
Title:
Failure to Test the Resilient Seal on the Outer Door of the Reactor Building Personnel Hatch Type: An abnormal occurrence as defined by the Technical Specifications,
paragraph 1.8g, in that the f ailure to test the resilient seal on the outer door of the Reactor Building Personnel Hatch represented an inadequacy in the administrative controls which threatened to cause an unsafe condition in the eratio of the plant.
) 4 2.
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0 (5) Conditions Prior to Occurrence:
Because of non-nuclear related maintenance, the plant was undergoing load changes during routine power operations with major parameters as follows :
Power: Core : 50%
12522 Elec.: 400 MW (Gross)
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. 6 RC Flow: 135 x 10 lb/hr RC Pressure: 2155 psig RC Temp.: 579 F PRZR Level: 220 in P RZR Temp. : 640 F (6) Description of Occtrrence:
Specification 4.4.1.2.5.b of the TMI-1 Technical Specifications requires that when not in a cold shutdown condition that the resilient seal on the outer door of the Reactor Building Personnel Hatch be tested after each use, but no more than once daily.
Contrary to this requirement, the Reactor Building Personnel Hatch was cpened several times during the period November 23-29, 1974, but the resilient seal on the outer air lock door was not tested.
(7) Designation of Apparent Cause of Occurrence:
Inadequate procedural guidance was the apparent cause of the occurrence in that there were no procedures in existence at the time of the occurrence to direct Operations Department personnel on when to test the resilient doo r s eal.
(8) Analysis of the Occurrence:
It is believed that failure to leak test the seal did not threaten either the health or safety of the public in that subsequent to the occurrence the seal was tested and found to be within specification limits.
(9) Corrective Action:
Immediate corrective action was taken as described above to verify the leak-tightness of the seal, at a meeting held soon af ter the occurrence was reported, the Plant Operations Review Committee reviewed and gave its approval of this action and recommended to the Station Superintendent that as a long-term action the "Shif t and Daily Checks" procedure be revised to include a check-off of whether the Personnel Access Hatch had been used and the door seal tested that day. The Station Euperintendent concurred with this recommendation and the procedure has been revised.
1484 199
(10) Failure Data:
Not Applicable.
Sincerely, R. C.
old Vice President RCA/JW/cas File :
20.1.1/7.7.3.5.1 cc:
Mr. J. P. O'Reilly (DORO-Region 1) 1484 200