ML19259D489

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Environ Incident 50-289/74-5:on 740608,excessive Chlorine in River Discharge Water Violated Ets.Caused by Varying River Conditions,River Cooling Water Transit Time & Lack of Proper Chlorine Feed Rate Guidelines
ML19259D489
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/14/1974
From: Arnold R
METROPOLITAN EDISON CO.
To:
References
GQL-0078, GQL-78, NUDOCS 7910240756
Download: ML19259D489 (5)


Text

AEC DIS _TR'UTION FOR PART 50 DOCKET MATERT'L, (TEMPORARY FORM)

CONTRO*. NO:

5485 FILE:

ENVIRO FROM:

DATE OF DOC DATE REC'D LTR TWX RPT OTHER Metropolitan Edison Company Reading, PA R. C. Arnold 6-14-74 6-18-74 X

TO:

ORIG CC OTHER SENT AEC PDR XXX J. P. O'Reilly 1

CLASS UNCLASE PROP INFO INPUT NO CYS REC'D DOCKET NO:

XXX 1

50-289 DESCRIPTION:

ENCLOSURES:

Ltr furn info re Enviro Incident #EI 50-289/

MNT EMWE 74-5 of 6-8-74 re excessive free chlorine concentration at the plant river discharge....

ACKNOWLEDGED.

PLANT NAME: THREE MILE ISLAND UNIT #1 F_OR ACTION /INFORMATION 6-20-74 GPC BUTLER (L)

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Dear Mr. O S Reilly :

Operating License DPR-50 Docket #50-289 In accordance with the Environmental Technical Specifications for Thra Mile Island Nuclear Station, Unit 1, we are reporting the follovir Jp,/,,4r.

s Environmental Incident:

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b (1) Reporting Number:

E.I. 50-289/Th-5 j

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JUN181974*{j; (2a) Report Date: June lh, 19Th EIGULUOM

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(2b) Occurrence Date:

June 8, 197h gyy dy' (3) Facility:

Three Mile Island Nuclear Generating Station, Unh le

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Identification of Incident:

Excessive Free Chlorine Concentration at the Plant River Discharee which is a violation of Environmental Technical Specifications, paragraph 2.2.la, and constitutes exceeding a liricing condition for operation.

(5) Conditions Prior to Occurrence:

Reactor critical, power escala-tron test at 05 of rated power in progress with nujor plant para-meters as follows:

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Power:

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0 RC Temperature:

532 F PRZR Level:

100 in.

FRZR Temp.:

65sCF (6)

Description of Incident:

During a periedic evolution conducted to chlorinate the syste=s cooled by the techanical draft cooling tower, the plent river discharge samples taken 10 and 30 ninutes after co==encement of the evolution indicated a free chlorine concentration of.10 pps.

In that chlorine addition had been terminated about 15 minutes after co=cencement of the evolution, it was deter =ined that there were no additional actions which could be taken to get the reading within the specification limit.

(7)

Designation of Apparent Cause of Incident:

a.

Procedure, in that there are no guidelines to aid in determining how the chlorine feed rate should be varied as a function of existing conditions.

Some of the conditions which can affect the amount of free chlorine consured as it passes through the syste=s include:

1.

River cooling water transit tire from the river cooling water pump discharge to the cooling tower discharge, which is in turn a function of the number of systems and pumps in use, and 2.

Various river water conditianc such as temperature, pH, and organic co= position.

It is also possible that there is a random variation in the concentration of chlorine in the river vacer.

Considering that in this incident the values for chlorine in the discharge water are at the limiting value of.10 ppm, even a slight variation could be significant.

b.

Although not considered to be the cause of this incident, the possibility exists for there having been a naterial failure in that :.he apparatus used to determine chlorine in the grab sa ples may have not functioned properly.

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(8)

Analysis of Incident :

It is believed that the level of free chlorine in the discharge water was not high enough and did not exist far a long enou-h period of time to have caused any environmental dar. age or to have endangered the health and safety of the public.

This belief is based on the following significant points of information:

a.

Chlorine addition was secured about 15 minu.2- ;rior to collection of the 30-minute sample.

Free chlorine in the 50-ninute sample was measured as o ppa.

b.

Total chlorine in the 10, 30, and 50-minute grab samples was measured cs.13,.12, and.00 pps, respectively.

All of these values are well below the.20 ppm limit given in the Technical Specifi-cations.

(9)

Corrective Action:

Immediate corrective action involving termination of chlorine addition was not possible because chlorine addition had already been ter=inated by the time it was realized the limiting value for free chlorine vould be exceeded, and no immediate actions were taken.

The Station Superintendent was notified of the incident.

He in turn infermed the Vice President-Generation and, to provide for an additional precautionary measure, it was then decided to decrease the chlorination feed rate slightly from the previous rate of 200 lbs/ day prior to the next chlorination period.

Additional long-term corrective actions relating to this same problem were stated in EI 50-289/7h-2 seven day letter dated June 5,197h, and II 50-289/74-3 seven day letter dated June 12, 197h, and will consist of:

a.

meeting with a consultant to discuss terms of a contract to evaluate 1.

if, and how, chlorine addition rates should be established as a function of existing conditions, and 2.

the reliability of the chlorine conitoring apparatus,

and b.

utilizing the yet-to-be-established 90-day period referenced in the Invironnental Technical Specifications, paragraph 2.2.1.b, to further evaluate (9)a.l. and (9)a.2. above.

(10) Failure Data:

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Previous Failures:

Although malfunctioning of the analytical apparatus used to teasure chlorine in the grab samples is not believed to 12 the cause of this incident, this p:asibility has been previously noted in EI 50-289/Th-2 seven-duy letter dated June 5,1974; EI 50-289/74-3 seven-day letter dated June 12,197L; er.d EI 50-289/Th-h seven-day letter dated June 13, 1974.

b.

Equipment Identification:

It vill not be poesible to ascertain if the monitoring apparatus failed until the additional technical analyses mentioned in (9)a. and (9)b. above are cc=pleted; however, on the casis of what information is available, failure of the equipment is considered to be unlikely.

Sincerely, Signed - R. C. Arnold R. C. Arnold Vice President ROA:JFV:lv cc:

Director Directorate of Licensin6 U. S. Atomic Energy Co==ission Washington, D. C.

205k5 File 20.1.1/7.7.3.11.1 1459 214

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