ML19210B343
| ML19210B343 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/20/1975 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210B344 | List: |
| References | |
| GQL-1740, NUDOCS 7911070601 | |
| Download: ML19210B343 (4) | |
Text
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NRC vlSTRIBUTION FOR PART 50 DOCh,ur MATERI AL
- (TEMPORARY FORM) 13311 CONTROL NO:
j FILE:
Enviro FROM: Metropolitan Edison Co.
DATE OF DOC DATE REC'D LTR TWX RPT OTHER Reading, Pa R.C. Arnold 11-20-75 11-24-75 xxxx
- TO:
ORIG CC OTHER SENT NRC PDR vvv.
Mr. J.P. O'Reilly none 1
SENT LOCAL PDR xvv CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
xxxx
'l 50-289 DESCRIPTION:
ENCLOSURES:
Ltr reporting Environmental Abnormal occurrence
- 75-9 on 11-13 concerning the temperature g
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differential between river water inlet and
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n discharge temperature change at a rate in
- excess of 2 F/hr.......
DO NC PLANT NAME: Three Mile Island #1
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FOR ACTION /INFC RMATJON 11-26-75 JGB BUTLER (L)
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POST OFFICE BOX 542 READING, PENNSYLVANIA 19603 TELEPHONE 215 - 929 3601 Nove=ber 20, 1975 GQL 17h0 a,- c, Fi.e Cy.
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Mr. J. P. O'Reilly, Director Office of Inspection and Enforce =ent, Region I Nuclear Regulatory Cc=sission 631 Park Avenue Kirgs of Prussia, Pennsylvania 19h06
Dear Mr. O'Reilly:
Operating License DPR-50 Docket No. 50-289 In accordance with t he Environmental Technical Specifications for Three Mile Island Nuclear Station Unit 1, we are reporting the following'65heqtal Incident:
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(1)
Reporting Nunber: E.I. 50-289/75-09 j[
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!U' (2a) Report Date: November 20, 1975
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ef",N.3 (2b) Occurrence Date:
Nove ter 13, 1975 VC a 5-WM> L
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(3)
Facility:
Three Mile Island Nuclear Generating Statiod,UniL3,f \\,'/
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Identification of Incident:
The temperature differential between river water inlet and discharge temperature changed at a rate in excess of 2 F/hr. which constitutes a violaticn of the Environmental Technical Specification 2.1.b. (2).
(5)
Conditions Prior to occurrence:
A rcutine shutdcun operation was in progress with =ajor plant parameters as fc11ovs:
Pover:
Core:
05 Elec.: 0%
RC Flow:
1500 gp: (Decay Heat Renoval Syste Flov)
)547 356 RC Fressure:
313 psig RC Tecp..
237 F 13311
PRZR Level: 110 in.
PRZR Te=p.: h20 F 6.
Description of Incident:
On November 18, 1975, during the cooldown of the reactor coolant syste=, the decay heat re= oval syste= vas placed into operation in accordance with the operating procedure.
The additional heat load i= posed on the river water syste= caused the effluent te=perature to rise from 52 F at 0650 to a maxi =u=
0 of 57 F at approximately 0720.
The operator observed the te=perature increase at approximately 0710 and i"-adiately started an extra mechanical draft cooling tower fan in slow speed mode to limit the temperature rise.
The effluent te=perature finally leveled off to 55 F at 0750. The effluent temperature change over the one (1) hour period (0650 to 0750) was 3 F/hr. which exceeded the Environmental Technical Specification limit of 2 F/hr.
T.
Designation of Apparent Cause of Incident:
The cause of this occurrence has been determined to be personnel / procedure in that the operator did not closely monitor the temperature change when placing the plant in the decay heat mode of operation. Additionally, adequate guidance may not be properly integrated into the shutdown procedure, decay heat removal procedure, decay heat river water procedure and the mechanical draft cooling tower operating procedure in order to adequately point out the actions which
=ust be taken by the operator to avoid exceeding the Environmental Technical Specifications limits on thermal discharges.
8.
Analysis of the Incident:
It is believed that the change in effluent te=perature of 3 F in one (1) hour did not cause any environmental damage in that the ccndition did not sub-stantially exceed the Environmental Technical Specifications limit of 2 F per hour, and was not so severe as to greatly alter the ambient temperature of the river.
The temperature difference between the inlet and outlet river water streans was well within the 200F limit allowed by the Environ = ental Technical Specifitions for a reactor cooldown condition (2.1.b. (2)).
Title 25, Pennsylvania Code, Secticn 97.82(a) states that the heat content of a discharge shall not change the temperature of the entire stream by more than 0
2 F during any one-hour period.
In addition, Environmental Technical Specifications paragraph 2.l(3), objective of the Thermal Limiting Condition of Operation states that, "the taxi =u= change in mixed river temperature shall not exceed 2 F/hr.".
It is our belief that the 3"F/hr. temperature difference experienced at TMI discharge did not ec= promise the thermal vater quality criteria of either the NRC cr the Cc==onwealth of Pennsylvania even though Environmental Technical Specificatien 2.1.b.(2) was violated.
9 Corrective Action:
In addition to the immediate action described above, the affected operating procedures will be reviewed and revised if necessary to assure the proper emphasis and guidance is given to the operator to closely observe the 1547 357
' effluent temperatures when placing the plant in the decay heat mode of operation.
10.
Failure Data:
Not Applicable.
Similar Occurrences: E.I. 74-1, E.I. 74-8, E.I. 75-7, E.I. 75-8.
Sincerely, Signed - R. C. Amald R. C. Arnold Vice President RCA:JIIC:tas cc:
Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Cc==ission Washington. D.C.
20555 File:
20.1.1 / 7.7.3.11.1 1547 358