ML19261F148
| ML19261F148 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/24/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-1755, NUDOCS 7910240888 | |
| Download: ML19261F148 (4) | |
Text
NRC ~9TRIBUTION FOR PART 50 DOCKr_-" MATERI AL (TEMPORARY FORM)
CONTROL NO: 13427 e
FILE: INCIDEM REPON "
FROM: Metropolitan Edison Co.
DATE OF DOC DATE REC'O LTR TWX RPT OTHER Reading, PA.
11-24-75 11-28-75 XXX p C. Arnold
- ~ -
TO:
ORIG CC OTHER SENT AEC PDR YYY D
NRC 1 Signid 0
SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
'l 50-289 XXX DESCRIPTION:
ENCLOSURES:
C'ncern-Abnormal Occurrence # 75-41, On 11-14-759 o
ing a increase in the radiation level.on the Reactor Building purge monitor.......
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an w oanss METROPOLITAN EDISON COMPANY PoGT OFFICE BOX 542 READING. PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 November 2h, 1975 1755
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Director of Nuclear Reactor Regulation J
Division of Reacter Licensing
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U. S. Nuclear Regulatory Cc: mission
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'Jashington, D.C.
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Dear Sir:
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Decket No. 50-269
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Operating License No. DPR-50 In accordance with the Technical Specifications of cur Three Mile Island Nuclear Station U nit 1 (TMI-1), we are reporting the folleving abnormal occurrence.
(1)
Report Number: A0 50-289/75-41 fg <r, b
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3 (2a)
Report Date:
November 2h, 1975 c -- n
- x um (2b)
Occurrence Date: November lh, 1975 (3)
Facility: Three Mile Island Nuclear Station Unit.1 3'".
~
,s (h)
Identificaticn of Occurrence:
s s
Title:
Failure of Operation's Personnel to Strictly' Folicv the Drain and Blanke+ Cperating Precedure.
Type: An abner =al occurrence as defined by tln Technical Specificaticns,
paragraph 1.8c and g, in that a written procedure relating to nuclear safety was not strictly adhe:ced to in all matters,
which constitutes a violation of Technical Specificatien 6.2.3.
(5)
Conditions Prior to ocet rrence:
Power:
Core: 0%
Elec.
0 :Ge RC Flev: 1500 rp= (Decay Heat Re= oval Flcv) 1482 295 RC Pressure: C psig 0
RC Temp.
Il0 F 13427
PRZR Level: h0 in.
PRZR Te=p..
130 F (6) Description of Occurrence:
On Nove=ter lh,1975, between the hours of 1736 and 22L5, a small increase in the radiation level on the Reacter Building purge radiatien moniter P11-A9 was observed. After a thorough check of the evolutiens occurring in the reactor building, it was disecvered that the center control red drive mechanism was vented to the building and was permitting radioactive gas to e olve frem the vented reactor coolant system to the reactor building. The v
vent was inmediately closed and gas samples were collected and evaluated to determine the radicactive isetcpes present.
An investigation into the reason why the centrol red drive techanist vent was lined-up directly to the Reactor Building atmosphere revealed that the reactor c 'lant system Drain and Blanket Ope-sting Precedure, 1103-11, was violated in that the control red was supposed to be connected and vented to the reacter coolant drain tank which is connected to the icv pressure vent header.
(7) Designation of Apparent Cause of Occurrence:
The cause of this occurrence has been determined to be rersonnel in that, the personnel involved in the venting operation implied that venting directly to the building would accomplish the same objectives as vould venting to the noeter coolant drain tank, as was specified by the procedure. When the vent line was initially installed samples were obtained at the vent area in order to ascertain that no release of radioactive gas vculd occur; however, in deviating frem the procedure requirements the cenditions were set up for an eventual unplanned release of radioactive gas to the reactor building.
(8) Analysis of Occurrence:
It has been determined that this occurrence did not constitute a threat to the health and safety of the public in that:
a.
Analysis of the reactor building purge duct radiation monitor Fl!-A9 recorder chart and RM-A9 gas sa:ples indicated the radicactive material released was predcminantly 133 Xe (98%) and that the instantaneous ncble gas release rate was 2.05 x 103 M3 5 fsec. which is
.s/sec.
The below the technical specification limits of 1.2 x 10 average release rate over the 5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 9 minute period of this release was 7.26 x 102 3
M /sec. with a total release of ncble gas of 3 98 curies.
b.
Although persennel vere in the reacter building at the time cf the release, analysis of the containment at=cspheric =cnitor, FLA2, indicated that the ccncentratien in the building did not exceed the unrestricted >TCa fcr the
=ixture of isotopes present.
'"herefore, no expcsure problem relative to the release existed.
gB2 2%
(9) Corrective Action:
In addition to the i=nediate acticn described above, the Operatien's personnel vill be counseled and cautioned that the written procedures used in the operatien of the plant shall be strictly adhered to in all matters relating to nuclear safety and that prior to changing the steps of precedures the proper netted of procedure changes must be folleved.
(10) Failure Data:
- let applicable.
Similar Occurrences: A0 50-289/75-38.
Since gly, P
R. C. krnold Vice President RCA :JMC :tas cc: Office of Inspection and Enforcement, Region 1 Ms. Margaret A. Reilly, Chief Bureau of Radiological Health Pa. Dept. of Environmental Resources F. O. Box 2063 Harrisburg, PA 17120 File:
20.1.1 / 7.7.3.1.1 1482 277