ML19261F339
| ML19261F339 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/07/1977 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19261F340 | List: |
| References | |
| GQL-0782, GQL-782, NUDOCS 7910250797 | |
| Download: ML19261F339 (4) | |
Text
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'ISSION DOCKET NUMBE R NRC FORu 195 R -2Q $
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NRC DISTRIBUTION FOR e' ART 50 DOCKET MATERI AL IN TO:
J.P.0'REILLY FROM: METROPOLITAN EDISON CO.
DATE OF OCCUMENT READING, PA.
A/7/77 J.G. HERBEIN DATE RECEIVED 6/11/77 SLETTER ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECE4VED
[ ORIGIN AL UUNCLASSIFIED CCCPY l $ ff g y DESCRIPTION ENCLOSU R E LTR TRANS THE FOLLOWING..t.....
LICENSEE EVENT REPORT FOR R.O.# 77-J3/4T, ON 5/23/77 CONCERNING SUSPENDED' SOLIDS CONCENTRATI 1:
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METROPOLil AN EDISON COMPANY POST OFFICE BOX 542 RE ADING, PENNSYLV ANI A 19603 TELEPHO" " - 909-2601 Q 101/
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Mr. J. P. O'Reilly, Director
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Office of Inspection and Enforcement, Region I D'"%* /&
U. S. Nuclear Regulatory Consissica
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King of Prussia. Pennsylvania 19hC6 RESULf0RY DOCIET fil.iCOPY Decket No. 50-289 Operating License No. DPR-50 It should be noted that this report is being filed one day late, in accordance with our telephone cenversation of June 6,1977 with Mr. McCabe of your staff.
In accordance with the Technical Specificatiens of our Three Mile Island Nuclear Station Unit 1 (TMI-1), we are reporting the following reportable occurrence:
(1) Report Number: 77-13/hT (2a) Required Report Date: 6/6/77 (2b) Date of Occurrence:
5/23/77 (3) Facility: Three Mile Island Nuclear Station - Unit 1 (h) Identification of Occurrence:
Title:
Suspended Solids Concentration of Station Discharge Greater Than Specified Maxi =un TYPE:
A reportable occurrence as defined by Envircnmental Technical Specification 2.2.2a in that the suspended solids concentratien at the plant river water discharge was measured to be greater than the specified maximun (560 ppm)
(5) Conditions prior to Occurrence Power: Core-700%
Elec:
831 MWe RC Flev-
'hhx10 lb/Hr RC Pressure:
2155 psig RC Tenp:
579 F PRZR Level:
220 inches PRZR Temp:
6550F (6) Description of Occurrence:
At Ch50 hours en May 23, 1977, approximately one hour after initiating the discharge from both Unit I and Unit II Waste Neutralicatien Tanks, a sample of the plut river sater discharge was obtained for analysis. The suspended 1482 076 m m...
June 7, 1977 Mr. J. P. O'Reilly JQL 07c2 solids analysis of this sa=ple was ec=pleted at 08h5 hours, on May 23, 1977, and the concentraticn was found to be 760 pp=.
The Shift Supervisor was notified and he i==ediately crdered the termination of both Unit I and Unit II Waste Neutralization Tank discharges. The Unit I discharge was stopped at 08h5 hours 23 May 1977. The Unit II discharge had already been terminated at 0800 hcurs 23 May 1977 Analysis of the suspended solids concentration in the Unit I Waste Neutralization Tank shewed 3h ppm and the Unit II Waste Neutralization Tank sample shoved 29 ppm. A river water influent sample cbtained at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> en May 23, 1977 had a suspended solids concentration of 20 pps.
At 0900 hcurs on that same day, a second sa=ple of the plant river water discharge was obtained and found to have a suspended solids concentration of 31h ppm which is well within the 560 ppm limit.
(7) Designation of Apparent Cause of Cccurrence:
Thorough investigation of the occurrence failed to determine the exact cause.
However, several possibilities exist.
(a) A leak was discovered in the discharge line frcm the sample pump (SR-Pk) which provides sa=ples of river water effluent. This could have induced the hideout of suspended solids in the piping downstream of the leak due to lowered flev velocities. The solids could then have breken loose during sa=pling and provided a sample with a suspended solids concentration greater than the representative effluent.
(b) A slug of suspended solids could have been pumped frcs the su=p of the inoperable Mat: Filter System. This sump collects spent pcvdered resins from the condensate polishing units, sludge frcm the pretreatment clarifiers and solids which are backvashed from the carbon filters. An analysis for suspended solids was performed on a sa=ple from this sump which was obtained at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> 23 May 1977 Results showed 213 ppm which would not have created the 760 ppm at the plant river water discharge. Ecwever, the concentration at 0h50 hours (the time at which the river discharge sa=ple was taken) =ay have been much higher. Also, the re=aining pcrtien of the plant river water discharge sa ple was sent to our GPU Systems Laboratory for further analysis. Using a scanning electron microscope, this lab verified the presence of resin particles, river dirt, and iron particles in the sa=ple which are all indicative of types of solids fcund in the Mat: filter su=p.
(c) Samples of other possible sources of high suspended solids were as follows:
Sample Date Time Sustended Solids (pp=)
Unit I Turbine Euilding Sanp 5/23/77 0930 8
Unit II Turbine Building Su=p 5/23/77 1020 30 Neither of these sources have as high a pctential for creating the proble as (a) or (b) above.
(d) The Unit I and Unit II Waste Neutralization Tanks were eliminated as pcssible causes due to them having only 3h and 29 ppm suspended sclids concentrations respectively.
In s"--a 7, either a slug of high concentration of suspended solids frem the Mat:
1482 077
June 7, 1977 72. J. P. O'Reilly GQL 0762 filter su=p or a peor sample due to the leak in the sample pu=p discharge line, er a combinatica cf these probably caused the occurrence.
(8) Analysis of Cecurrence:
Assuming that the suspended solids concentration at the plant river water discharge was actually 760 ppa, it is believel that this did not cause any environmental damage to the biota of the Susquehanna River. It shculd te noted that durine; periods of high river water levels, the suspended solids concentrations in our river influent have exceeded 560 pp=.
(9) Ccrrective Action In addition to the i==ediate Corrective Action described above:
(a) A work request was initiated to repair the leaking sample pump discharge line to insure that representative samples are obtained.
(b) Interi= measures for treatment of suspended solids frc= the Mate Filter Building tre being investigated. These measures could possib'y reduce the suspended solids concentration frc= this source until the permanent Industrial Waste Filter System is constructed.
The Industrial Waste Filter System is scheduled to be cperational by March 1,1978.
The Plant Operation Review Committee and Unit Superintendent have reviewed and approved the above corrective action, and have taken steps to assure its cc=-
pletien.
(10) Failure Date: N/A Similar Events:
(List of Similar Unusual Occurrences by Report Number)
EI 75-Oh Sincerely, 1'
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J. G. Herbein Vice President JGH:RAL:J=r
Enclosure:
License Event Report Form.
1482'078