ML19210A152

Nonroutine 10-Day Rept 75-09 Re Unplanned Release of Radioactivity.Overflow of Reactor Coolant Into Auxiliary Bldg Sump Caused by Operator Confusing B & C Bleed Tanks.No Tech Spec Limits Exceeded

ML19210A152
Person / Time
Site:	Three Mile Island
Issue date:	12/05/1975
From:	Arnold R METROPOLITAN EDISON CO.
To:
References
GQL-1780, NUDOCS 7910240877
Download: ML19210A152 (4)

Text

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• ' CONTROL NO:13685 _

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XXX I 50-289 DESCRIPTION: ENCLOSURES:

Letter trans the following.......

- Ncrroutine 10-Day Report, Concerning an Un-P1:nned Release of Radioacti.ve Material Which occurred on- 11-.25-75... ... .

. (1 Copy Received) j ._b PLANT NAME:Three Mile Island # 1 FOR ACTION /INFORbATION SAB 12-10-75 BUTLER (L) SCHWENCER (L) ZIEMANN (L) REG AN (E)

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POST OFFICE BOX 542 READING PENNSYLVANI A 1960'i fM- TELEPHONE 215 - 929-3601 December 5, 1975- -

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Dear Sir:

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Docket No. 50-289 Operating License DPR-50 Nonroutine 30-Day Report 15-09 In accordance with Section c.7.2.a.2 of the Technical Specifications for our Three Mile Island Nuclear Station Lnit 1, enclosed please find Nonrcutine 10-Day Report 75-09 that deals with ar unplanned release of radicactive naterial which occurred on November 25, 1975 We vould like to point out that no meet .' of the public and no station er centractor personnel received a radiation dose in excess of the limits stated in 10 CM1 20 as a result of the release. Further, ncne o-l the limits given in the Technical Specifications were exceeded.

We trust that this satisfies the reporting requirements referenced abcve and adequateJy answers any concerns you =ay have.

Sincerely, o

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R. C. arnold Vice President RCA:JMC:ilm File: 20.1.1/7 7.3.12.1 Fnclosure: Nonreutine 10-Day Report 75-09 cc: Mr. J. P. O'Reilly, (U.S. NRC -hegion 1)

Ms. Margaret Reilly (Fa. DEE) 1490 068 13685

4 e NCN-ROUTIiE 1C DAY RE?CRT T5-09 REFCRT OF A'i LCIPLANNED RELEASE OF PADICTI7E MATERIAL CCCURRING ON NOVEMEER 25, 1975 Descriptien of Occurrence Cn November 25, 1975, between the hours of 1754 and 1835, (forty-one (hl) minutes) an inadvertant release of radioactive material occurred duc to the overflev cf approximately eight (800) hundred gallons of reactor coolant frcm the "B" Reacter Ccolant Bleed Tank into the Auxiliary Euilding Susp.

The "3" Reacter Coolant Bleed Tank, which was fu21 at the time, was incorrectly chosen as the tank into which the primary system vculd be letdevn during bleed and feed operations. The overficv of the tank drained to the Auxiliary Building Sunp. Radicactive gases dissolved in the ccolant evolved into the sump air spcce which is ventilated directly into the Auxiliary Building Ventilation Exhaust System. Due to the lcw concentration of caterial released, no alarms were received on the Auxiliary Building Ventilaticn Exhaust Monitcr (RM-AS). Centrol Rocm pers.nnel noticed the increase in the Auxiliary Building sunp level and terminated tne letdcun to the "B" Bleed Tank, thereby, terminating the release.

Apparent Cause of the Occurrence Personnel errer was the apparent cause of the occurrence in that the operator confused the level indication of "3" Bleed Tank, which was full, and the "C" Bleed Tank, which was nearly empty.

Analyc4s of the Occurrence Fcr the following reason: it is believed that the unplanned release of radicactive material en the 25th of :Tovember did not endanger either the health cr safety of the public.

a. Ncne of the limits in the TMI-1 Technical Specifications were exceeded.

b. Ncne of the naximum permissible concentration limit: fer non-radiaticn verkers as given in 10 CFR 20 vere exceeded at the site boundary.

c. No individual on site at the time of the release received a radiaticn dose in excess of the limits for radiatien verkers specified in 10 CFR 20.

Corrective Action The 12:ediate corrective acticn was to transfer the letdevn frc the "3" Bleed Tank to the "C" Eleed Tank. The cperater involved was cautiened to be more careful when reading instrumentatien.

1490 069

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Failure Data Not Applicable Release Data NCTE: In no case did any = ember of the public or any station er centractor perscnnel receive a radiation dose near the applicable limits given in 10 CFR 20.

The total release consisted of .118 curies of predominantly Xel33 (assumed to be 100%) based on Radiation Monitoring Systes Scrip Chart Recordings.

The maximum instantanecus noble gas release rate during the forty-cne (1.1) minute period was 3.8 :.102 M3/sec. which is below the Technical Specification limit of 1.2 x 10 3 M 3 /sec. The average release rate during the pericd was 1.cl x 102 M3 /sec. There vere no personnel exposures involved during the release since there were no persennel in t he Auxiliary 3uilding Susp (a nermally unoccupied area).

1490 070