ML19261F210
| ML19261F210 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/17/1974 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-0080, GQL-80, NUDOCS 7910250628 | |
| Download: ML19261F210 (4) | |
Text
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- ?.!EU"'ICN FCR PART 50 DOCKET M/
IAL (TEMPORARY FORM)
CONTROL NO:
5573 FILE:
PROM:
Metropolitan Edison Company Reading, Pa. 19603 6-17-74 6-20-74 X
R. C. Arnold ID:
D. L.
1 sigt. _d SENT LOCAL PDR X CLASS UNCLASS PROP IN70 INPUT NO CYS REC'D 1 DOCKET NO:
XXX 1
50-289 DESCRIPTION:
ENCLOSURES:
Ltr reporting abnormal occurrence A0 50-289/74
-8 on 6-6-74, regarding improper gain setting for nuclear overpower trip instrument.....
ACKNOWLEDGED DO NOT REMOVE PLANT NAME: Three Mila Island Unit #1 FOR ACTION /INFORMATION 6-20-74 GC BUTLER (L)
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xa m Regulatory _ Docket File METROPOLITAN EDISON COMPANY PCCT OFFICE BOX 5J2 RE AclNG, PENNSYLV ANI A 196C3 TELEPHONE 215 - 929-2001 June 17, 197h GQL 0C66-
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Dear Sir:
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Operating License DFB-50
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Decket No. 50-289 Ir. accordance with the Technical Specifications for the Three Mile Island Nuclear Station, Unit 1, we are reporting the following abnormal occur-rence:
(1)
Report Number:
A0 50-289/7h-8 (2a) Report Date:
June 17, 197h (2b) Cccurrence Date: June 6, 197h (3)
Facility: Three Mile Island Nuclear Generr31ng Station, Unit 1 (h)
Identificatien c' Occurrence:
Title:
5 m cer Cain Setting for Nuclear OverpcVer Trip
_ c muent Type:
An abncr=al occurrence as defined by the Technical Specifications, paragraph 1.8b, in that the improper gain setting for channel 3 nuclear overpever trip instrument resulted in exceeding a limiting condition for operatica as defined by the Technical Specifi-cations, paragraph 3.1.9.1.b.
(5)
Conditiens Frier to Cecurrence: Reacter critical, lcw pcVer physics testing in progress, with =ajor plant parameters as follevs:
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Pcver:
Core:
0 Elec.: 0 148t 158 v,e) i d
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U1 rector June 17, 197L RC Flav:
lh2 x 10 lbs/hr RC Pressure: 2155 psig RC Te=p:
531 F PRZR Level:
100 in.
PRZR Temp.:
650 F (6) Descriptisa of Occurrence: At the time of the cccurrence, e heat balance calibration of the pcVer rang 2 instrumentation had never been conducted in that the reacter had never been taken to a pcVer level above or equal to the peint of sensible heat. During low pcVer physit aesting, therefore, to assure the nuclear over-pcVer trip would occur at less than 5% rated pcVer, reacter pro-tection syste= settings were conservatively ec=puted and censerva-tively selected to ccrrespend to a 2 5% nuclear everpower trip.
During a spct check of the Reactor Protection Syste= settings, it was found that ene of the settings (channel B linear a=plifier) was set at a value which, in accordance with the conservative assumptiens, corresponded to a 20% nuclear ever-power trip.
Operations personnel prc=ptly conducted checks of reactor protec-tion channels A, C, and D (which were found to have correct settings),
and an approved procedure was used to reset the reacter protection channel B linear amplifier to the correct setting.
(7) Designation of Apparent Cause of Occurrence: For the surveillance test which checks the linear amplifier B settings, procedure calls for the linear a=plifier setting to be changed to a standard test setting, and then to be reset to the correct setting prior to test ec=pletien. The test progra= procedures and the nuclear overpower trip instru=ent surveillance procedure vere not interfaced sufficiently to ensure that special instrunent settings required for the test progra= vere utilized for final setting of the instru=ent adjustments and, therefore, the apparent cause of this occurrence is Procedure.
(8) Analysis of Occurrence:
It is believed this ocaurrence pcsed no potential danger to public health and safety in that a subsequent sensible heat determination indicates the incerrect setting on the channel B linear amplifier corresponded to a highest possible power level of enly 10%, instead of the conservatively ec=puted 20%. Also, at least 2 additional protection channels were cperative during the course of the occurrence, and the protection system requires caly 2 channels to initiate a reactor shut-devn signal.
(9) Cerrective Actions:
I=nediate acticns were as described in the above analysis.
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' Director June 17, 197h
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The Plant Operatiens Review Ccc=ittee (PCRC) =et prc=ptly after the occurrence and recctmended to the Statien Superintendent that apprc-priate warnings and/cr cautions be added to the surveillt.nce prece-dure to ensure adequate interface with the special require =ents of the start-up and test progra= procedures.
The Station Superintendent has cencurred with PCRC's recccrendation, and has directed the appropriate procedural changes be initiated.
(10) Failure Data:
(a) Previous Failures: Not Applicable.
(b) Equipment Identification: Not Applicable.
Sincerely, 1
R7 C.
- nold Vice President-Generation RCA:DNG:pa ec: Directorate of Regulatory Operations, Region 1 U.S. Atetic Energy Coc=issict.
631 Park Avenue King of Prussia, Pennsylvania 19h06 1481 160