ML19259D516

Environ Incident 50-289/75-06:on 750804,dissolved Solids Concentration of River Water Exceeded Ets.Caused by Discharge Rate Higher than Effective River Water Dilution Rate.Pumping Rate Change Will Allow for Greater Dilution

ML19259D516
Person / Time
Site:	Three Mile Island
Issue date:	08/09/1975
From:	Arnold R METROPOLITAN EDISON CO.
To:
References
GQL-1377, NUDOCS 7910240779
Download: ML19259D516 (4)

Text

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. NRC Dit '9UTION FOR PART 50 DOCKET f _TERI AL

• • (TEMPORARY FORM)

FILE: [W/ M C LTR TWX RPT OTHER FROM: Metropolitan Edison Co DATE OF DOC DATE REC'D Reading, Pa 8-11-75 XXX a c arnold 8-9-75 XX ORIG CC OTHER SENT NRC PDR TO: U Mr O'Reilly none signed SENT LOCAL PDR INPUT NO CYS REC'O DOCKET NO:

CLASS UNCLASS PROPINFO 1 50-289 XXu ,

ENCLOSURES:

DESCRIPTION:

Ltr reporting abnormal occurrence #75-06 (Enviro) on 8-4-75 concerning an excessi "e .

MGiOWLEDGED concentration of dissolved soldds as mea sured at the plant river water discharge

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FOR ACTION /INFORMATION REG AN (E)

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POST OFFICE BOX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-3601 August 9, 1975 GQL 1377 Mr. J. P. O'Reilly, Director Office of Inspection and Enforcement, Region 1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. O' Reil'.y:

Operating License DPR-50 Docket No. 50-289 In accordance with the Environmental Technical Specifications for Three Mile Island Nuclear Station Unit 1, we are reporting the following Environmental Incident:

(1) Report Number: E.I. 50-289/75-06 (2a) Report Date: August 9, 1975 (2b) Occurrence Date: August 4, 1975 (3) Facility: Three Mile Island Nt e- lear Station Unit 1 (TMI-1)

(4) Identification of Incident:

The dissolved solids concentration as measured at the plant river water discharge exceeded 700 ppm, which is a violation of the Environmental Technical Specifications, paragraph 2.2.2a, and constitutes a limiting condition for operation.

(5) Conditions Prior to Incident:

The reactor was at steady state power with plant paraneters as follows:

Power: Core: 100% j f } g },g }

, 4%)hh N' Elect: 860 MW (Gross)

RC Flow: 142 x 10 6 lb/hr / 'Y ,

c e CN O RC Pressure: 2155 psig 7

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RC Temp: 579 F .

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-s s PRZR Level: 240 in.

PRZR Temp: 6550F (6) Description of Incident:

On August 4,1975, a Preoperational Cleaning sad Flushing Settling Basin was being neutralized and discharged to the river in accordance with Special Operating Procedure 226. The Suttling Basin currently is being discharged for approximately eight hours a day. The daily river water discharge sample was drawn at 1255. The analysis of the sample, which requires approximately four hours, indicated the dissolved solids concentration to be 821 ppm. This analysis was not completed until the normal discharge had been secured for the day. On August 5, 1975, the discharge of the Settling Basin was restarted. The out-of-specification August 4 condition was recognized at approximately 1000 on August 5 when sample analysis results were reviewed by Supervisory Personnel and the discharge was terminated.

(7) Designation of Apparent Cause of Incident:

The apparent cause of the incident is procedur e , in that dhe waste basins were being discharged at too great a rate (750 gpm), for dilution with river water to be effective. Further, with regard to procedure, at a pumping rate of 750 gpm, the amount of 10% sulfuric acid being added for neutralization is a contributing factor to the dissolved solid concentration. The sulfuric acid addition to the effluent stream fluctuates, thus varying its contribution to the total dissolved solids discharged. Even though the acid metering varies the pH is maintained between 6.0 and 9.0. It is also possible that the waste basins are stratified causing differing values of dissolved solids, both horizontally and vertically over the langth of the basin. No adverse effects on the river biota were observed and there was no threat to the health and safety of the public as a result of this incident.

(8) Analysis of Incident:

It is believed that this incident did not threaten the environment in that no adverse effects on river ecosystems or biota were observed.

(9) Corrective Action:

Immediate corrective action was taken as described above to terminate the release. Long term corrective action will be taken as follows:

a. Special Operating Procedure 226 will be amended to include a more informative sampling schedule. The effluent sample will be drawn approximately one hour after initiating discharge and analysis will commence immediately. Each day before securint, the discharge, a basin sample will be drawn and analyzed to provide data for the next day's releases.

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The pH wi.'.1 be maintained in the upper portion of the allowable range to minimize the contribution to dissolved solids from the acid addition (i.e. pH control system) . In addition, the waste basin will be allowed to settle with no recirculation of contents after securing the discharge each day,

b. All Chemistry Department personnel will be re-instructed in the Technical Specification requirements and limits. A program will be developed to insure direct feedback to the Chemistry Supervisory staff of Technical Specification parameters for accelerated

' evaluation and action.

c. The pumping rate from the pits will be reduced from the present rate of 750 gpm to approrhtely 550 gpm. This will allow for adequate dilution of the discharge.

The actions were reviewed and approved by the Plant Operations Review Committee and the Station Superintendent, and the Station Superintendent has taken steps to insure that they are implemented.

(10) Failure Data:

Not Applicable Sincerely, Signed R. C. Arnold R. C. Arnold Vice President RCA:RSB:tas File: 20.1.1 / 7.7.3.11.1 cc: Director Division of Reactor Licensing .

U. S. Nuclear Regulatory Commission Washington, D.C. 20555 1459 287