ML19261F283
| ML19261F283 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/26/1974 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| References | |
| GQL-0354, GQL-354, NUDOCS 7910250725 | |
| Download: ML19261F283 (5) | |
Text
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AEC DISTRIBUTION FOR PART 50 DOCKET MATERI AL (TEMPOR ARY FORM)
CONTROL NO: 10064 FILE:
FROM Metropolitan Edison Co DATE OF DOC DATE REC'D LTR TWX RPT OTHER Reading Pa 19603 A Arnold 9-26-74 9 30-74 XXX TO:
ORIG CC OTHER SENT AEC PDR XX XX DL 1 signed SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:
XXXXX 1
50-289 DESCRIPTION:
ENCLOSURES:
Ltr re Abnormal Occurrence #74-16 on 9-16-74 ACKNOWLEDGED concerning inadequate administrative and pro-cedural control of radiation monitoring syste:r DO NOT REMOVE calibration.............
PLANT NAME:Three Mile Island #1 FOR ACTION /INFORMATION 10-3-74 BUTLER (L)
SCHWENCER (L) ZIEM ANN (L)
REGAN (E)
W/ Cocies W/ Copies W/ Copies W/ Copies CLARK (L)
STOLZ (L)
DICKER (E)
LEAR (L)
W/ ' Copies W/ Copies W/ Copies W/ajCopies PAR R (L)
VASSALLO (L)
KNIGHTON (E)
W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L)
PURPLE (L)
YOUNGB LOOD (E)
W/ Copies W/ Copies W/ Cocies W/ Copies INTERNAL DISTRISUTION trN G FI LE TECH REVIEW DENTON LIC AE3T A/T IN D E
t/A to c u rs GRIMES BRAITMAN
/SCHROEDER GAMMILL DIGGS (L)
SALTZMAN
[VOGC ROOM P 506A /l.lACCARY KASTNER GEARIN (L)
- 8. HURT 1UNTZING/ STAFF ytASE
/,KNIG H T BALLARD GOULBOURNE (L)
GI AM BUSSO (P AWLICKl SPANG LE R KREUTZER (E)
PLANS BOYD
- SHAO LEE (L)
MCDOLLD MOORE (L) (BWR) e/STE LLO ENVIRO M AIG R ET (L)
CHAPMAN DEYOUNG (L) (PWR)./ HOUSTON MULLER REED (E)
DUBE w/ input DICKER SERVICE (L)
E. COUPE SKOVHOLT (L)
/y/NOVAK ROSS KNIGHTON SHEPPARD (L)
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/TEDESCO REGAN SMITH (L) cfKLECKER gfREG OPR g/LONG PROJECT LDR AEETS (L)
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METROPOLITAN EDISON COMPANY DO2T CF8'CE BCX 542 AE AO!NG. PENNSYLV ANT A 19CO3 TELEPwCNE 215 - 929CCG1 SEP 2 61974 G;I 035h itegulatory File C'y7 Directorate of Licensing U. S. Atomic Energy Co==ission Washington, D. C.
205h5
Dear Sir:
Operating License DPR-50 Docket No. 50-269 In accordance with the Technical Specifications for our Three Mile Islanc' Nuclear Sts..lon, Unit 1, we are reporting the following abncr:al occurrence:
1.
Report Number: A0 50-289/7h-16 2 a. Report Date: September 26, 197h 2b.
Occurrence Date: September 16, 197h 3
Facility: Three Mile Island Nuclear Station, Unit 1 h.
Identification of Occurrence:
Title:
Inadequate Administrative and Procedural Contrcl of Radiation Monitoring Syste: Calibraticn Type: An abnormal occurrence as defined by the Technical Specifications, paragraph 1.8g., in that the Inadequate Administrative and Procedural Ccntrol of Radiaticn Mcnitcring System Calibraticn threatened to cause an unsafe condition in the operation of the plant.
5 Cor litions Prior to occurrence:
The reacter was at steady state power with major plant parameters as follevs:
e, d[i.s s
/
Power: Core: 100",
Elec: 856 MW (Grcss)
Q f f' i
j 6
b $$p301en
\\48\\h RC Flow: 138 x 10 lbs/hr RC Pressure: 2155 psig c gi 10064 4 -w.i D s/ ~w j * -a
Directorate of Licensing $2P 2 6 1574 4 RC Temp.: 579 F PRZR Level: 260 in. PRZR Temp.. 650 F 6. Descriptica of Occurrence: On September 16,197h, it was observed that portions of the Radiation Monitoring System had not been calibrated in accordance with the quarterly =enitoring requirement of the Technical Specifications, Table h.1-1, ite: 28. This quarterly calibra-tion should have been completed by June 30,197h. 7 Designation of Apparent Cause of Occurrence: It is believed that the occurrence was due primarily to inade-quate crocedures, in that pcrtions of the calibration procedure were not technically consistent with the de sign of the Radiation Monitoring System. Secondarily, inadequate administrative controls contributed to the occurrence, in that while plant management was aware that equipment and procedure problems did exist, they were not aware that these problems were causing interruptions in the calibration program. 8. Analysis of Occurrence: For the following reascns it is believed that the failure of plant personnel to calibrate a portion of the Radiation Mcnitoring System did not represent a threat to either the health or sa'ety of the public: a. The Radiatien Monitoring System was successfully calibrated in April,197h, during the Startup and Test Program. b. Of the 26 liquid, gas, and air =cniters not calibrated, approximately two thirds had had their alert and alarm set points checked by the required date. c. All routine Reactor Building purges, Waste Gas Eecay Tank releases, and liquid releases were analyzed for their specific isotopic characteristics prior to being released. This analysis indicated that all radioactivity parameters would be well vithin the allevable limits specified by the Technical Specifications. d. The unplanned September 5-7,197h, releases frc= the Auxiliary Building (letter of informatien in preparation) centained levels of radiation belev those allowed by the Technica' Specifications.
ec, e :.. ~~; Directorate of Licensing ' 9 Corrective Actica: I ediate corrective actions taken were as follcva: a. The plant technical staff developed a temporary change notice to the quarterly calibration procedure based upon the experience to date and the technical canual and calibrated all channels which had exceeded their calibration interval. b. Concurrent with the calibraticn effort, the procedure fcr quarte rl',r calibration was redrafted for review and approval. When the revised approved procedure is available, the Radiation Monitoring System quarterly calibration vill be rerun so that current locumentaticn based upon the revised procedure is on file. c. The Station Superintendent directad appropriate plant super-vision to review surveillance test < -hedules and results en a weekly basis. d. The Vice President of Generatien appointed a special investi-gating co==ittee of off-site perscnnel with appropriate qualifications to fully review the circumstances preceding the incident and to develop recc==endations for technical, procedural, and administrative corrective acticn. Long term corrective action vill be determined after review of the report from the special co=mittee. 10. Failure Data: Not applicable. Sincerely, 1) fl C del Vice Ebesident RCA: DUG :sh ec: Mr. J. P. O' Reilly \\h0\\ File 20.1.1 7.T.3.5.1
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p G(, =ffetss,-s pt,,a ' monomnan cason cosecan, P O Box 542, Rea&ng, Pa 19603 ( Director Directorate of Licensing U. S. Atomic Energy Commission 1 20545 Washington, D. C. e. CO A' N O 9}}